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1

Iterative model-building, structure refinement, and density modification with the PHENIX AutoBuild Wizard  

E-Print Network [OSTI]

Iterative model-building, structure refinement, and densitytool for iterative model- building, structure refinement andusing RESOLVE or TEXTAL model- building, RESOLVE statistical

Terwilliger, T. C.; Los Alamos National Laboratory, Mailstop M888, Los Alamos, NM 87545, USA; Lawrence Berkeley National Laboratory, One Cyclotron Road, Building 64R0121, Berkeley, CA 94720, USA; Department of Haematology, University of Cambridge, Cambridge CB2 0XY, England

2008-01-01T23:59:59.000Z

2

ITER  

SciTech Connect (OSTI)

This year six international partners have signed up to construct the first burning plasma experiment -- ITER -- in the South of France.It is over 50 years since the beginning of national programs to produce controlled fusion energy. The challenge of fusion energy has proven harder than was first anticipated. In this Colloquium Steve Cowley from UCLA will explain the scientific issues and how the difficulties have been overcome.

Cowley, Steve

2005-10-10T23:59:59.000Z

3

Nested Loop Algorithm for Parallel Model Based Iterative Reconstruction  

E-Print Network [OSTI]

Nested Loop Algorithm for Parallel Model Based Iterative Reconstruction Zhou Yu, Lin Fu, Debashish. In this paper, we propose a fast converging simultaneous-update algorithm using a nested loop structure tomography, iterative reconstruction, nested loop, preconditioner. I. INTRODUCTION Recent applications

4

Error Control of Iterative Linear Solvers for Integrated Groundwater Models  

E-Print Network [OSTI]

and presentation of GMRES performance benchmarking results. Introduction As the groundwater model infrastructureError Control of Iterative Linear Solvers for Integrated Groundwater Models by Matthew F. Dixon1 for integrated groundwater models, which are implicitly coupled to another model, such as surface water models

Bai, Zhaojun

5

Accelerated Iterative Method for Solving Steady Solutions of Linearized Atmospheric Models  

E-Print Network [OSTI]

Accelerated Iterative Method for Solving Steady Solutions of Linearized Atmospheric Models Masahiro approach, referred to as the accelerated iterative method (AIM), is developed for solving steady state, respectively. For ensuring the accelerated asymptotic convergence of iterative procedure

Watanabe, Masahiro

6

STELLOPT Modeling of the 3D Diagnostic Response in ITER  

SciTech Connect (OSTI)

The ITER three dimensional diagnostic response to an n=3 resonant magnetic perturbation is modeled using the STELLOPT code. The in-vessel coils apply a resonant magnetic perturbation (RMP) fi eld which generates a 4 cm edge displacement from axisymmetry as modeled by the VMEC 3D equilibrium code. Forward modeling of flux loop and magnetic probe response with the DIAGNO code indicates up to 20 % changes in measured plasma signals. Simulated LIDAR measurements of electron temperature indicate 2 cm shifts on the low field side of the plasma. This suggests that the ITER diagnostic will be able to diagnose the 3D structure of the equilibria.

Lazerson, Samuel A

2013-05-07T23:59:59.000Z

7

Modeling results for the ITER cryogenic fore pump  

SciTech Connect (OSTI)

The cryogenic fore pump (CFP) is designed for ITER to collect and compress hydrogen isotopes during the regeneration process of torus cryopumps. Different from common cryopumps, the ITER-CFP works in the viscous flow regime. As a result, both adsorption boundary conditions and transport phenomena contribute unique features to the pump performance. In this report, the physical mechanisms of cryopumping are studied, especially the diffusion-adsorption process and these are coupled with standard equations of species, momentum and energy balance, as well as the equation of state. Numerical models are developed, which include highly coupled non-linear conservation equations of species, momentum and energy and equation of state. Thermal and kinetic properties are treated as functions of temperature, pressure, and composition. To solve such a set of equations, a novel numerical technique, identified as the Group-Member numerical technique is proposed. It is presented here a 1D numerical model. The results include comparison with the experimental data of pure hydrogen flow and a prediction for hydrogen flow with trace helium. An advanced 2D model and detailed explanation of the Group-Member technique are to be presented in following papers.

Zhang, D. S.; Miller, F. K.; Pfotenhauer, J. M. [University of Wisconsin-Madison, Madison, WI 53706 (United States)

2014-01-29T23:59:59.000Z

8

Power Transmission From The ITER Model Negative Ion Source  

SciTech Connect (OSTI)

In Cadarache development on negative ion sources is being carried out on the KAMABOKO III ion source on the MANTIS test bed. This is a model of the ion source designed for the neutral beam injectors of ITER. This ion source has been developed in collaboration with JAERI, Japan, who also designed and supplied the ion source. Its target performance is to accelerate a D- beam, with a current density of 200 A/m2 and <1 electron extracted per accelerated D- ion, at a source filling pressure of 0.3 Pa. For ITER a continuous ion beam must be assured for pulse lengths of 1000 s, but beams of up to 3,600 s are also envisaged. The ion source is attached to a 3 grid 30 keV accelerator (also supplied by JAERI) and the accelerated negative ion current is determined from the energy deposited on a calorimeter. During long pulse operation ({<=}1000 s) it was found that the current density of both D- and H- beams, measured at the calorimeter was lower than expected and that a large discrepancy existed between the accelerated currents measured electrically and those transmitted to the calorimeter. The possibility that this discrepancy arose because the accelerated current included electrons (which would not be able to reach the calorimeter) was investigated and subsequently eliminated. Further studies have shown that the fraction of the electrical current reaching the calorimeter varies with the pulse length, which led to the suggestion that one or more of the accelerator grids were distorting due to the incident power during operation, leading to a progressive deterioration in the beam quality.. New extraction and acceleration grids have been designed and installed, which should have a better tolerance to thermal loads than those previously used. This paper describes the measurements of the power transmission and distribution using these grids.

Boilson, D. [Association EURATOM-DCU, PRL/NCPST, Glasnevin, Dublin 13 (Ireland); Esch, H. P. L. de; Grand, C.; Hemsworth, R. S.; Krylov, A. [Association EURATOM-CEA, CEA/DSM/DRFC, CEA-Cadarache, 13108 St Paul-Lez-Durance (France)

2007-08-10T23:59:59.000Z

9

Characterization of the ITER model negative ion source during long pulse operation  

SciTech Connect (OSTI)

It is foreseen to operate the neutral beam system of the International Thermonuclear Experimental Reactor (ITER) for pulse lengths extending up to 1 h. The performance of the KAMABOKO III negative ion source, which is a model of the source designed for ITER, is being studied on the MANTIS test bed at Cadarache. This article reports the latest results from the characterization of the ion source, in particular electron energy distribution measurements and the comparison between positive ion and negative ion extraction from the source.

Hemsworth, R.S.; Boilson, D.; Crowley, B.; Homfray, D.; Esch, H.P.L. de; Krylov, A.; Svensson, L. [Association EURATOM-CEA, CEA Cadarache, F-13108, St. Paul lez Durance (France); Association EURATOM-DCU, PRL/NCPST, Glasnevin, Dublin 13 (Ireland); Euratom/UKAEA Fusion Association, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); Association EURATOM-CEA, CEA Cadarache, F-13108, St. Paul lez Durance (France)

2006-03-15T23:59:59.000Z

10

Ab initio modeling of small proteins by iterative TASSER simulations  

E-Print Network [OSTI]

(< 120 residues) were used. I-TASSER folded four of them with a C?-RMSD < 2.5Å. The average C?-RMSD of the I-TASSER models was 3.9Å, whereas it was 5.9Å using TOUCHSTONE-II software. Finally, 20 non-homologous small proteins (< 120 residues) were taken...

Wu, Sitao; Skolnick, Jeffrey; Zhang, Yang

2007-05-08T23:59:59.000Z

11

Data augmentation for a Bayesian spatial model involving censored observations  

E-Print Network [OSTI]

Data augmentation for a Bayesian spatial model involving censored observations Brooke L Fridley1 (fax) 1 #12;SUMMARY Spatial environmental data sometimes include below detection limit observations (i. We develop a measurement error Bayesian spatial model for the analysis of spatial data with censored

12

Modeling of modification experiments involving neutral-gas release  

SciTech Connect (OSTI)

Many experiments involve the injection of neutral gases into the upper atmosphere. Examples are critical velocity experiments, MHD wave generation, ionospheric hole production, plasma striation formation, and ion tracing. Many of these experiments are discussed in other sessions of the Active Experiments Conference. This paper limits its discussion to: (1) the modeling of the neutral gas dynamics after injection, (2) subsequent formation of ionosphere holes, and (3) use of such holes as experimental tools.

Bernhardt, P.A.

1983-01-01T23:59:59.000Z

13

AMPERE 2011, Toulouse Modeling -372 An Iterative Routine for Macroscopic Modeling of  

E-Print Network [OSTI]

. The developed approach involves two software packages: QuickWave-3D, a simulator that uses the conformal finite for energy savings and faster processing of ceramic and metallic powders. The main benefit in comparison. This paper addresses the problem of numerical simulation of micro- wave sintering at a macroscopic scale

Yakovlev, Vadim

14

Implementation of the Iterative Proportion Fitting Algorithm for Geostatistical Facies Modeling  

SciTech Connect (OSTI)

In geostatistics, most stochastic algorithm for simulation of categorical variables such as facies or rock types require a conditional probability distribution. The multivariate probability distribution of all the grouped locations including the unsampled location permits calculation of the conditional probability directly based on its definition. In this article, the iterative proportion fitting (IPF) algorithm is implemented to infer this multivariate probability. Using the IPF algorithm, the multivariate probability is obtained by iterative modification to an initial estimated multivariate probability using lower order bivariate probabilities as constraints. The imposed bivariate marginal probabilities are inferred from profiles along drill holes or wells. In the IPF process, a sparse matrix is used to calculate the marginal probabilities from the multivariate probability, which makes the iterative fitting more tractable and practical. This algorithm can be extended to higher order marginal probability constraints as used in multiple point statistics. The theoretical framework is developed and illustrated with estimation and simulation example.

Li Yupeng, E-mail: yupeng@ualberta.ca; Deutsch, Clayton V. [University of Alberta (Canada)

2012-06-15T23:59:59.000Z

15

Policy Iteration / Optimistic Policy Iteration Least-Squares Policy Iteration Experiments Least Squares Policy Iteration  

E-Print Network [OSTI]

Policy Iteration / Optimistic Policy Iteration Least-Squares Policy Iteration Experiments Least Squares Policy Iteration Bias-Variance Trade-o in Control Problems Christophe Thiéry and Bruno Scherrer/27 #12; Policy Iteration / Optimistic Policy Iteration Least-Squares Policy Iteration Experiments Markov

Scherrer, Bruno

16

Models for source term, flow, transport and dose assessment in NRC`s Iterative Performance Assessment, Phase 2  

SciTech Connect (OSTI)

The core consequence modules for the recently completed Phase 2 Iterative Performance Assessment (IPA) of the Yucca Mountain repository for high-level nuclear waste depend on models for releases from the engineered barrier system (source term), flow of liquid and gas, transport of radionuclides in the geosphere and assessment of dose to target populations. The source term model includes temperature and moisture phenomena in the near-field environment, general, pitting and crevice corrosion, contact of the waste form by water, dissolution and oxidation of the waste form, and transport of dissolved and gaseous radionuclides from the waste package by advection and diffusion. The liquid flow and transport models describe water flow through fractures and matrix in both the unsaturated and saturated zones. Models for flow of gas and transport of {sup 14}CO{sub 2} released from the engineered barrier system to the atmosphere take into account repository heat and the geothermal gradient. The dose assessment model calculates doses to a regional population and a farm family for an assumed reference biosphere in the vicinity of the repository. The Phase 2 IPA led to a number of suggestions for model improvement: (1) improve the ability of the models to include spatial and temporal variability in the parameters; (2) improve the coupling among processes, especially the effects of changing environments in the waste packages; (3) develop more mechanistic models, but abstracted for use in total system performance assessment; and (4) use more site specific parameters, especially for the dose assessments.

McCartin, T.; Codell, R.; Neel, R.; Ford, W.; Wescott, R.; Bradbury, J. [Nuclear Regulatory Commission, Washington, DC (United States); Sagar, B.; Walton, J. [Center for Nuclear Waste Regulatory Analyses, San Antonio, TX (United States)

1994-12-31T23:59:59.000Z

17

Non-degenerate shell-model effective interactions from the Okamoto-Suzuki and Krenciglowa-Kuo iteration methods  

E-Print Network [OSTI]

We present calculations of shell-model effective interactions for both degenerate and non-degenerate model spaces using the Krenciglowa-Kuo (KK) and the extended Krenciglowa-Kuo iteration method recently developed by Okamoto, Suzuki {\\it et al.} (EKKO). The starting point is the low-momentum nucleon-nucleon interaction $V_{low-k}$ obtained from the N$^3$LO chiral two-nucleon interaction. The model spaces spanned by the $sd$ and $sdpf$ shells are both considered. With a solvable model, we show that both the KK and EKKO methods are convenient for deriving the effective interactions for non-degenerate model spaces. The EKKO method is especially desirable in this situation since the vertex function $\\hat Z$-box employed therein is well behaved while the corresponding vertex function $\\hat Q$-box employed in the Lee-Suzuki (LS) and KK methods may have singularities. The converged shell-model effective interactions given by the EKKO and KK methods are equivalent, although the former method is considerably more efficient. The degenerate $sd$-shell effective interactions given by the LS method are practically identical to those from the EKKO and KK methods. Results of the $sd$ one-shell and $sdpf$ two-shell calculations for $^{18}$O, $^{18}$F, $^{19}$O and $^{19}$F using the EKKO effective interactions are compared, and the importance of the shell-model three-nucleon forces is discussed.

Huan Dong; T. T. S. Kuo; J. W. Holt

2011-05-23T23:59:59.000Z

18

ITER Project  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr FlickrGuidedCH2MLLCBasicsScience at ALCFPhysicsQuality AssuranceITER

19

Physical Models of Noncovalent Interactions Involving Aromatic Rings  

E-Print Network [OSTI]

-aromatic rings are often quite favourable. For example, the above computed interaction energies for model ethene-benzene and butadiene-benzene complexes are substantial (–0.85 and –1.50 kcal mol–1 for ethene and butadiene, respectively). In the latter case...

Bloom, Jacob Walter Goldstein

2014-04-17T23:59:59.000Z

20

Review of recent experimental and modeling progress in the lower hybrid range of frequencies at ITER relevant parameters  

SciTech Connect (OSTI)

Progress in experiment and simulation capability in the lower hybrid range of frequencies at ITER relevant parameters is reviewed. Use of LH power in reactor devices is motivated in terms of its potential for efficient off-axis current profile control. Recent improvements in simulation capability including the development of full-wave field solvers, inclusion of the scrape off layer (SOL) in wave propagation codes, the use of coupled ray tracing/full-wave/3D (r v{sub ?}, v{sub //}) Fokker Planck models, and the inclusion of wave scattering as well as nonlinear broadening effects in ray tracing / Fokker Planck codes are discussed. Experimental and modeling results are reviewed which are aimed at understanding the spectral gap problem in LH current drive (LHCD) and the density limit that has been observed and mitigated in LHCD experiments. Physics mechanisms that could be operative in these experiments are discussed, including toroidally induced variations in the parallel wavenumber, nonlinear broadening of the pump wave, scattering of LH waves from density fluctuations in the SOL, and spectral broadening at the plasma edge via full-wave effects.

Bonoli, Paul T. [Plasma Science and Fusion Center, NW16-240, MIT, Cambridge, Massachusetts 02139 (United States)

2014-06-15T23:59:59.000Z

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Review of recent experimental and modeling progress in the lower hybrid range of frequencies at ITER relevant parameters  

SciTech Connect (OSTI)

Progress in experiment and simulation capability in the lower hybrid range of frequencies (LHRF) at ITER relevant parameters is reviewed. Use of LH power in reactor devices is motivated in terms of its potential for efficient off-axis current profile control. Recent improvements in simulation capability including the development of full-wave field solvers, inclusion of the scrape off layer (SOL) in wave propagation codes, the use of coupled ray tracing / full-wave / 3D (r v{sub ?}, v{sub ?}) Fokker Planck models, and the inclusion of nonlinear broadening effects in ray tracing / Fokker Planck codes are discussed. Experimental and modeling results are reviewed which are aimed at understanding the spectral gap problem in LH current drive (LHCD) and the density limit that has been observed in LHCD experiments. Physics mechanisms that could be operative in these experiments are discussed, including toroidally induced variations in the parallel wavenumber, nonlinear broadening of the pump wave, scattering of LH waves from density fluctuations in the SOL, and spectral broadening at the plasma edge via full-wave effects.

Bonoli, Paul T. [Plasma Science and Fusion Center, NW16-240, MIT, Cambridge, MA 02139 (United States)

2014-02-12T23:59:59.000Z

22

A multi-scale iterative approach for finite element modeling of thermal contact resistance  

E-Print Network [OSTI]

Surface topography has long been considered a key factor in the performance of many contact applications including thermal contact resistance. However, essentially all analytical and numerical models of thermal contact ...

Thompson, Mary Kathryn, 1980-

2007-01-01T23:59:59.000Z

23

US ITER Moving Forward  

ScienceCinema (OSTI)

US ITER Project Manager Ned Sauthoff, joined by Wayne Reiersen, Team Leader Magnet Systems, and Jan Berry, Team Leader Tokamak Cooling System, discuss the U.S.'s role in the ITER international collaboration.

US ITER / ORNL

2012-03-16T23:59:59.000Z

24

On the Logic of Iterated Non-prioritised Richard Booth  

E-Print Network [OSTI]

, and of iterated revision [3, 5, 7, 8, 17, 21], i.e., the study of the behaviour of an agent's beliefs underOn the Logic of Iterated Non-prioritised Revision Richard Booth Department of Computer Science. We look at iterated non-prioritised belief revision, using as a starting point a model of non

Booth, Richard

25

ECRH System For ITER  

SciTech Connect (OSTI)

A 26 MW Electron Cyclotron Heating and Current Drive (EC H and CD) system is to be installed for ITER. The main objectives are to provide, start-up assist, central H and CD and control of MHD activity. These are achieved by a combination of two types of launchers, one located in an equatorial port and the second type in four upper ports. The physics applications are partitioned between the two launchers, based on the deposition location and driven current profiles. The equatorial launcher (EL) will access from the plasma axis to mid radius with a relatively broad profile useful for central heating and current drive applications, while the upper launchers (ULs) will access roughly the outer half of the plasma radius with a very narrow peaked profile for the control of the Neoclassical Tearing Modes (NTM) and sawtooth oscillations. The EC power can be switched between launchers on a time scale as needed by the immediate physics requirements. A revision of all injection angles of all launchers is under consideration for increased EC physics capabilities while relaxing the engineering constraints of both the EL and ULs. A series of design reviews are being planned with the five parties (EU, IN, JA, RF, US) procuring the EC system, the EC community and ITER Organization (IO). The review meetings qualify the design and provide an environment for enhancing performances while reducing costs, simplifying interfaces, predicting technology upgrades and commercial availability. In parallel, the test programs for critical components are being supported by IO and performed by the Domestic Agencies (DAs) for minimizing risks. The wide participation of the DAs provides a broad representation from the EC community, with the aim of collecting all expertise in guiding the EC system optimization. Still a strong relationship between IO and the DA is essential for optimizing the design of the EC system and for the installation and commissioning of all ex-vessel components when several teams from several DAs will be involved together in the tests on the ITER site.

Darbos, C.; Henderson, M.; Gandini, F. [JTER Organization, 13067 Saint Paul-Lez-Durance cedex (France); Albajar, F.; Bomcelli, T.; Heidinger, R.; Saibene, G. [Fusion for Energy, C/Josep Pla 2, Torres Diagonal Litoral-B3, E-08019 Barcelona-Spain (Spain); Bigelow, T.; Rasmussen, D. [US ITER Project Office, Oak Ridge National Laboratory, 055 Commerce Park, PO Box 2008, Oak Ridge, TN 37831-6483 (United States); Chavan, R.; Goodman, T.; Hogge, J. P.; Sauter, O. [Association EURATOM-Confederation Suisse, EPFL Ecublens, CH-1015 Lausanne (Switzerland); Denisov, G. [Institute of Applied Physics Russian Academy of Sciences, 46 Ulyanov Street, Nizhny Novgorod, 603950 (Russian Federation); Farina, D. [Istitutodi Fisica del Plasma, Association EURATOM-ENEA-CNR, Milano (Italy); Kajiwara, K.; Kasugai, A.; Kobayashi, N.; Oda, Y.; Ramponi, G. [Japan Atomic Energy Agency (JAEA) 801-1 Mukoyama, Naka-shi, Ibaraki 311-0193 (Japan)] (and others)

2009-11-26T23:59:59.000Z

26

On the Strategy and Requirements for Neutronics Testing in ITER  

SciTech Connect (OSTI)

Neutronics testing is among the several types of fusion technology testing scheduled to be performed in ITER. The three ports assigned for testing will test several blanket concepts proposed by the various parties with test blanket modules (TBM) that utilize different breeders and coolants. Nevertheless, neutronics issues to be resolved in ITER-TBM are generic in nature and are important to each TBM type. Dedicated neutronics tests specifically address the accuracy involved in predicting key neutronics parameters such as tritium production rate, TPR, volumetric heating rate, induced activation and decay heat, and radiation damage to the reactor components. In this paper, we address some strategies for performing the neutronics tests. Tritium self-sufficiency cannot be confirmed by testing in ITER, however, the testing can provide valuable information regarding the main parameters needed to assess the feasibility of achieving tritium self-sufficiency. The paper also addresses the operational requirement (i.e. flux and fluence) as well as the geometrical requirement of the test module (i.e. minimum size) in order to have meaningful and useful tests. Measured neutronics data require high spatial resolution. This necessitates that the measured quantity be as flat as possible in the innermost locations inside the test module. This requirement has been confirmed in the present work based on results from two-dimensional calculations. The US and Japan solid breeder test blanket modules are placed inside half a port in ITER. The R-{theta} model used accounts for the presence of the ITER shielding blanket and the surrounding frame of the port.

Youssef, M.Z. [University of California-Los Angeles (United States); Sawan, M.E. [University of Wisconsin-Madison (United States)

2005-05-15T23:59:59.000Z

27

Use of the iterative solution method for coupled finite element and boundary element modeling; Yucca Mountain Site Characterization Project  

SciTech Connect (OSTI)

Tunnels buried deep within the earth constitute an important class geomechanics problems. Two numerical techniques used for the analysis of geomechanics problems, the finite element method and the boundary element method, have complementary characteristics for applications to problems of this type. The usefulness of combining these two methods for use as a geomechanics analysis tool has been recognized for some time, and a number of coupling techniques have been proposed. However, not all of them lend themselves to efficient computational implementations for large-scale problems. This report examines a coupling technique that can form the basis for an efficient analysis tool for large scale geomechanics problems through the use of an iterative equation solver.

Koteras, J.R.

1993-07-01T23:59:59.000Z

28

ITER MHD stability analysis. Final report  

SciTech Connect (OSTI)

This report summarizes the final results and conclusions from work done for ITER under the DOE Task 18 (Raytheon Task ITER-GA 4002E). The work was performed in collaboration with D. Pearlstein and R. Bulmer of the Lawrence Livermore National Laboratory (LLNL), in close conjunction with D. Boucher of the ITER Joint Central Team (JCT). The work was partly done at General Atomics in San Diego and partly at LLNL. Approximately eight hours per week were spent from August 1994 through June 1995, with a no-cost extension through December 1995. The report covers work on the ideal MHD stability analysis for the ITER TAC scenarios and DIII-D ITER Demonstration Discharges, code modifications performed in order to efficiently and accurately complete the stability calculations, and additional collaborative efforts involving code benchmarking and dissemination of the DIII-D ITER Demonstration Discharge data. The work spawned several presentations and reports, including significant contributions to published IAEA Proceedings, and these are also summarized. 8 refs., 9 figs.

Turnbull, A.D.

1996-05-01T23:59:59.000Z

29

A test of the continuous spontaneous localization model involving two particles  

E-Print Network [OSTI]

We describe a previously unexplored effect of the continuous spontaneous localization model whereby a correlation develops in the distributions of two nearby non-interacting particles following a period of diffusion. We propose the use of this effect as an experimental test differentiating between the continuous spontaneous localization model and standard quantum theory. The test involves building a joint probability distribution for the locations of the two particles by repeatedly releasing them from two nearby traps and subsequently measuring their positions after a brief period of time. We examine the scales of time, trap size, and particle mass necessary for observation.

Daniel Bedingham

2014-11-26T23:59:59.000Z

30

Status of ITER Negotiations Warren Marton  

E-Print Network [OSTI]

for decommissioning. · ITER parties met in Barcelona, Feb. 7-11, to complete the technical level negotiations construction, & costs for operation, deactivation, and decommissioning required much interaction with all · Last issue is the complicated matter of P&I and waiver thereto, involving French Nuclear Safety

31

ITER convertible blanket evaluation  

SciTech Connect (OSTI)

Proposed International Thermonuclear Experimental Reactor (ITER) convertible blankets were reviewed. Key design difficulties were identified. A new particle filter concept is introduced and key performance parameters estimated. Results show that this particle filter concept can satisfy all of the convertible blanket design requirements except the generic issue of Be blanket lifetime. If the convertible blanket is an acceptable approach for ITER operation, this particle filter option should be a strong candidate.

Wong, C.P.C.; Cheng, E.

1995-09-01T23:59:59.000Z

32

The second iteration of the Systems Prioritization Method: A systems prioritization and decision-aiding tool for the Waste Isolation Pilot Plant: Volume 2, Summary of technical input and model implementation  

SciTech Connect (OSTI)

The Systems Prioritization Method (SPM) is a decision-aiding tool developed by Sandia National Laboratories (SNL). SPM provides an analytical basis for supporting programmatic decisions for the Waste Isolation Pilot Plant (WIPP) to meet selected portions of the applicable US EPA long-term performance regulations. The first iteration of SPM (SPM-1), the prototype for SPM< was completed in 1994. It served as a benchmark and a test bed for developing the tools needed for the second iteration of SPM (SPM-2). SPM-2, completed in 1995, is intended for programmatic decision making. This is Volume II of the three-volume final report of the second iteration of the SPM. It describes the technical input and model implementation for SPM-2, and presents the SPM-2 technical baseline and the activities, activity outcomes, outcome probabilities, and the input parameters for SPM-2 analysis.

Prindle, N.H.; Mendenhall, F.T.; Trauth, K.; Boak, D.M. [Sandia National Labs., Albuquerque, NM (United States); Beyeler, W. [Science Applications International Corp., Albuquerque, NM (United States); Hora, S. [Hawaii Univ., Hilo, HI (United States); Rudeen, D. [New Mexico Engineering Research Inst., Albuquerque, NM (United States)

1996-05-01T23:59:59.000Z

33

Plans for US Contributions to ITER U.S. ITER Plans for US Contributions to ITER  

E-Print Network [OSTI]

windings 75% cooling for divertor, vacuum vessel, ... 20% blanket/shield pellet injector tokamak exhaust supplies #12;Plans for US Contributions to ITER U.S. ITER Plans for US Contributions to ITER December 4 Exploring: - Seam-less tube conduit - Perforated central cooling tube #12;Plans for US Contributions to ITER

34

Nuclear Forensic Inferences Using Iterative Multidimensional Statistics  

SciTech Connect (OSTI)

Nuclear forensics involves the analysis of interdicted nuclear material for specific material characteristics (referred to as 'signatures') that imply specific geographical locations, production processes, culprit intentions, etc. Predictive signatures rely on expert knowledge of physics, chemistry, and engineering to develop inferences from these material characteristics. Comparative signatures, on the other hand, rely on comparison of the material characteristics of the interdicted sample (the 'questioned sample' in FBI parlance) with those of a set of known samples. In the ideal case, the set of known samples would be a comprehensive nuclear forensics database, a database which does not currently exist. In fact, our ability to analyze interdicted samples and produce an extensive list of precise materials characteristics far exceeds our ability to interpret the results. Therefore, as we seek to develop the extensive databases necessary for nuclear forensics, we must also develop the methods necessary to produce the necessary inferences from comparison of our analytical results with these large, multidimensional sets of data. In the work reported here, we used a large, multidimensional dataset of results from quality control analyses of uranium ore concentrate (UOC, sometimes called 'yellowcake'). We have found that traditional multidimensional techniques, such as principal components analysis (PCA), are especially useful for understanding such datasets and drawing relevant conclusions. In particular, we have developed an iterative partial least squares-discriminant analysis (PLS-DA) procedure that has proven especially adept at identifying the production location of unknown UOC samples. By removing classes which fell far outside the initial decision boundary, and then rebuilding the PLS-DA model, we have consistently produced better and more definitive attributions than with a single pass classification approach. Performance of the iterative PLS-DA method compared favorably to that of classification and regression tree (CART) and k nearest neighbor (KNN) algorithms, with the best combination of accuracy and robustness, as tested by classifying samples measured independently in our laboratories against the vendor QC based reference set.

Robel, M; Kristo, M J; Heller, M A

2009-06-09T23:59:59.000Z

35

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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36

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUSUS ITER

37

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUSUS ITER6 News

38

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUSUS ITER6 News7

39

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUSUS ITER6 News78

40

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUSUS ITER6 News789

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41

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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42

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUSUS ITER6Videos

43

The physics role of ITER  

SciTech Connect (OSTI)

Experimental research on the International Thermonuclear Experimental Reactor (ITER) will go far beyond what is possible on present-day tokamaks to address new and challenging issues in the physics of reactor-like plasmas. First and foremost, experiments in ITER will explore the physics issues of burning plasmas--plasmas that are dominantly self-heated by alpha-particles created by the fusion reactions themselves. Such issues will include (i) new plasma-physical effects introduced by the presence within the plasma of an intense population of energetic alpha particles; (ii) the physics of magnetic confinement for a burning plasma, which will involve a complex interplay of transport, stability and an internal self-generated heat source; and (iii) the physics of very-long-pulse/steady-state burning plasmas, in which much of the plasma current is also self-generated and which will require effective control of plasma purity and plasma-wall interactions. Achieving and sustaining burning plasma regimes in a tokamak necessarily requires plasmas that are larger than those in present experiments and have higher energy content and power flow, as well as much longer pulse length. Accordingly, the experimental program on ITER will embrace the study of issues of plasma physics and plasma-materials interactions that are specific to a reactor-scale fusion experiment. Such issues will include (i) confinement physics for a tokamak in which, for the first time, the core-plasma and the edge-plasma are simultaneously in a reactor-like regime; (ii) phenomena arising during plasma transients, including so-called disruptions, in regimes of high plasma current and thermal energy; and (iii) physics of a radiative divertor designed for handling high power flow for long pulses, including novel plasma and atomic-physics effects as well as materials science of surfaces subject to intense plasma interaction. Experiments on ITER will be conducted by researchers in control rooms situated at major fusion laboratories around the world, linked by high-speed computer networks--thus extending further what is already a much-acclaimed paradigm for international collaboration in science.

Rutherford, P.H.

1997-04-01T23:59:59.000Z

44

ITER Fusion Energy  

ScienceCinema (OSTI)

ITER (in Latin ?the way?) is designed to demonstrate the scientific and technological feasibility of fusion energy. Fusion is the process by which two light atomic nuclei combine to form a heavier over one and thus release energy. In the fusion process two isotopes of hydrogen ? deuterium and tritium ? fuse together to form a helium atom and a neutron. Thus fusion could provide large scale energy production without greenhouse effects; essentially limitless fuel would be available all over the world. The principal goals of ITER are to generate 500 megawatts of fusion power for periods of 300 to 500 seconds with a fusion power multiplication factor, Q, of at least 10. Q ? 10 (input power 50 MW / output power 500 MW). The ITER Organization was officially established in Cadarache, France, on 24 October 2007. The seven members engaged in the project ? China, the European Union, India, Japan, Korea, Russia and the United States ? represent more than half the world?s population. The costs for ITER are shared by the seven members. The cost for the construction will be approximately 5.5 billion Euros, a similar amount is foreseen for the twenty-year phase of operation and the subsequent decommissioning.

Dr. Norbert Holtkamp

2010-01-08T23:59:59.000Z

45

Regional groundwater modeling of the saturated zone in the vicinity of Yucca Mountain, Nevada; Iterative Performance Assessment, Phase 2  

SciTech Connect (OSTI)

Results of groundwater modeling of the saturated zone in the vicinity of Yucca Mountain are presented. Both a regional (200 {times} 200 km) and subregional (50 {times} 50 km) model were used in the analyses. Simulations were conducted to determine the impact of various disruptive that might take place over the life span of a proposed Yucca Mountain geologic conditions repository on the groundwater flow field, as well as changes in the water-table elevations. These conditions included increases in precipitation and groundwater recharge within the regional model, changes in permeability of existing hydrogeologic barriers, a:nd the vertical intrusion of volcanic dikes at various orientations through the saturated zone. Based on the regional analysis, the rise in the water-table under Yucca Mountain due to various postulated conditions ranged from only a few meters to 275 meters. Results of the subregional model analysis, which was used to simulate intrusive dikes approximately 4 kilometers in length in the vicinity of Yucca Mountain, showed water-table rises ranging from a few meters to as much as 103 meters. Dikes oriented approximately north-south beneath Yucca Mountain produced the highest water-table rises. The conclusions drawn from this analysis are likely to change as more site-specific data become available and as the assumptions in the model are improved.

Ahola, M.; Sagar, B. [Southwest Research Inst., San Antonio, TX (United States). Center for Nuclear Waste Regulatory Analyses

1992-10-01T23:59:59.000Z

46

ITER breeding blanket design  

SciTech Connect (OSTI)

A breeding blanket design has been developed for ITER to provide the necessary tritium fuel to achieve the technical objectives of the Enhanced Performance Phase. It uses a ceramic breeder and water coolant for compatibility with the ITER machine design of the Basic Performance Phase. Lithium zirconate and lithium oxide am the selected ceramic breeders based on the current data base. Enriched lithium and beryllium neutron multiplier are used for both breeders. Both forms of beryllium material, blocks and pebbles are used at different blanket locations based on thermo-mechanical considerations and beryllium thickness requirements. Type 316LN austenitic steel is used as structural material similar to the shielding blanket. Design issues and required R&D data are identified during the development of the design.

Gohar, Y.; Cardella, A.; Ioki, K.; Lousteau, D.; Mohri, K.; Raffray, R.; Zolti, E. [ITER Joint Central Team, Garching (Germany)] [and others

1995-12-31T23:59:59.000Z

47

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's central magnet requires

48

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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49

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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50

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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51

ITER blanket designs  

SciTech Connect (OSTI)

The ITER first wall, blanket, and shield system is being designed to handle 1.5{plus_minus}0.3 GW of fusion power and 3 MWa/m{sup 2} average neutron fluence. The reference shielding blanket (non breeding) uses austenitic steel structural material and water coolant with a copper first wall coated with beryllium. The first wall is protected by beryllium bumper limiters. The choice of copper first wall is dictated by the surface heat flux values anticipated during ITER operation. The water coolant is used at low pressure and low temperature. Liquid lithium is used as tritium breeder and coolant to alleviate issues of coolant breeder compatibility and reactivity. A layer of beryllium is incorporated in the blanket to improve the shielding performance and to insure tritium self-sufficiency. In addition, a shielding zone is incorporated at the back of the blanket to allow rewelding the vacuum vessel material during the ITER lifetime. The lithium coolant velocity required to remove the nuclear heating and the surface heat flux is 2 m/s, which produces a pressure drop of 0.6 MPa. Vanadium alloy (V-5Cr-5Ti) is being considered as the structural material because it can accommodate high heat loads and has good mechanical properties at high temperatures, high neutron fluence capability, low degradation under irradiation, good compatibility with liquid lithium, low decay heat, low waste disposal rating, and adequate strength to accommodate the electromagnetic loads during plasma disruption events.

Gohar, J.; Parker, R.; Rebut, P.H. [ITER Garching Joint Work Site, Garching bei Munchen (Germany)

1994-12-31T23:59:59.000Z

52

SciDAC Center for Simulation of Wave-Plasma Interactions - Iterated Finite-Orbit Monte Carlo Simulations with Full-Wave Fields for Modeling Tokamak ICRF Wave Heating Experiments - Final Report  

SciTech Connect (OSTI)

This final report describes the work performed under U.S. Department of Energy Cooperative Agreement DE-FC02-08ER54954 for the period April 1, 2011 through March 31, 2013. The goal of this project was to perform iterated finite-orbit Monte Carlo simulations with full-wall fields for modeling tokamak ICRF wave heating experiments. In year 1, the finite-orbit Monte-Carlo code ORBIT-RF and its iteration algorithms with the full-wave code AORSA were improved to enable systematical study of the factors responsible for the discrepancy in the simulated and the measured fast-ion FIDA signals in the DIII-D and NSTX ICRF fast-wave (FW) experiments. In year 2, ORBIT-RF was coupled to the TORIC full-wave code for a comparative study of ORBIT-RF/TORIC and ORBIT-RF/AORSA results in FW experiments.

Choi, Myunghee [Retired] [Retired; Chan, Vincent S. [General Atomics] [General Atomics

2014-02-28T23:59:59.000Z

53

The Pugh Controlled Convergence Method: Model-Based Evaluation and Implications for Design Theory  

E-Print Network [OSTI]

This paper evaluates the Pugh Controlled Convergence method and its relationship to recent developments in design theory. Computer executable models are proposed simulating a team of people involved in iterated cycles of ...

Wijnia, Ype

54

Report of panel 1: The appropriate scope and mission of ITER  

SciTech Connect (OSTI)

This panel looked at the mission of ITER, and how the US should address the present plans, and considers a number of alternative plans to arrive at the eventual goals of ITER. The panel considered three major approaches which have been discussed on the international scale, and tries to present the strengths, weaknesses, and possible changes to these plans. It suggests that any of these plans can arrive at the eventual aim, but may involve differing risks and time commitments. All plans involve ITER design studies, development work on technologies which must be in place for ITER design to succeed, and testing of materials and components for application in the device.

Linford, R.K. (Los Alamos National Lab., NM (United States)); Weitzner, H.; Abdou, M.A.; Baldwin, D.E.; Berkner, K.H.; Berry, L.A.; Culler, F.L.; Dean, S.O.; DeFreece, D.A.; Gauster, W.B. (and others)

1992-12-01T23:59:59.000Z

55

US ITER | About  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 - 20 Publications 1.HowUPF:USsITER

56

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's central magnet requires a

57

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's central magnet requiresUS

58

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's central magnetORNL's Fusion

59

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's central magnetORNL's FusionUS

60

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's central magnetORNL's

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNew Procurement

62

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUS Production of

63

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUS Production

64

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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65

What is ITER  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption byAbout PrintableBlenderWhat Makes Clouds Form, GrowWhat is ITER?

66

US ITER | About  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIA Energy Conference U.S. Crude OilITER Movingprime

67

US ITER | About  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIA Energy Conference U.S. Crude OilITER

68

US ITER | About  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIA Energy Conference U.S. CrudeElectronPelletIonITER

69

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIA Energy ConferenceKelli KizerUS ITER Major

70

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIA Energy ConferenceKelli KizerUS ITER MajorIn

71

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIA Energy ConferenceKelli KizerUS ITER MajorIntest

72

US ITER | Media Corner  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIA Energy ConferenceKelli KizerUS ITER

73

Department of Energy ITER Project  

E-Print Network [OSTI]

of operation to meet demand, and manageable waste. Currently, the ITER project is at the stage where the final responsible for procurements of in-kind hardware in its own territory with its own currency, a direct) for the base estimate consisting of about $4 billion for ITER hardware, initial spares, buildings

74

US ITER Project Providing a Facility for  

E-Print Network [OSTI]

US ITER Project Providing a Facility for Burning Plasma Research Ned Sauthoff Project Manager, US to position the US for Burning Plasma Research #12;U.S. ITER / Sauthoff Slide 2 Structure of the Talk... ITER

75

Contents of ITER deal revealed The Yomiuri Shimbun (May 27, 2005, 4 am)  

E-Print Network [OSTI]

in thermonuclear fusion. The country also will supply 20 percent of workers to ITER facilities. The four other on the roles of host and non-hosting countries involved in the International Thermonuclear Experimental Reactor. The planned ITER is an experimental facility for a thermonuclear reactor designed to produce power by fusing

76

U.S. Plans and Strategy for ITER Blanket Testing  

SciTech Connect (OSTI)

Testing blanket concepts in the integrated fusion environment is one of the principal objectives of ITER. Blanket test modules will be inserted in ITER from Day 1 of its operation and will provide the first experimental data on the feasibility of the D-T cycle for fusion. With the US rejoining ITER, the US community has decided to have strong participation in the ITER Test Blanket Module (TBM) Program. A US strategy for ITER-TBM has evolved that emphasizes international collaboration. A study was initiated to select the two blanket options for the US ITER-TBM in light of new R and D results from the US and world programs over the past decade. The study is led by the Plasma Chamber community in partnership with the Materials, PFC, Safety, and physics communities. The study focuses on assessment of the critical feasibility issues for candidate blanket concepts and it is strongly coupled to R and D of modeling and experiments. Examples of issues are MHD insulators, SiC insert viability and compatibility with PbLi, tritium permeation, MHD effects on heat transfer, solid breeder 'temperature window' and thermomechanics, and chemistry control of molten salts. A dual coolant liquid breeder and a helium-cooled solid breeder blanket concept have been selected for the US ITER-TBM.

Abdou, M. [UCLA Fusion Engineering Sciences (United States); Sze, D. [UCSD Advanced Energy Technology Group (United States); Wong, C. [General Atomics (United States); Sawan, M. [University of Wisconsin Fusion Technology Institute, Madison (United States); Ying, A. [UCLA Fusion Engineering Sciences (United States); Morley, N.B. [UCLA Fusion Engineering Sciences (United States); Malang, S

2005-04-15T23:59:59.000Z

77

Development of structural design criteria for ITER.  

SciTech Connect (OSTI)

The irradiation environment experienced by the in-vessel components of fusion reactors such as HER presents structural design challenges not envisioned in the development of existing structural design criteria such as the ASME Code or RCC-MR. From the standpoint of design criteria, the most significant issues stem from the irradiation-induced changes in material properties, specifically the reduction of ductility, strain hardening capability, and fracture toughness with neutron irradiation. Recently, Draft 7 of the interim ITER structural design criteria (ISDC), which provide new rules for guarding against such problems, was released for trial use by the ITER designers. The new rules, which were derived from a simple model based on the concept of elastic follow up factor, provide primary and secondary stress limits as functions of uniform elongation and ductility. The implication of these rules on the allowable surface heat flux on typical first walls made of type 316 stainless steel and vanadium alloys are discussed.

Majumdar, S.

1998-06-22T23:59:59.000Z

78

ITER Diagnostic First Wal  

SciTech Connect (OSTI)

The ITER Diagnostic Division is responsible for designing and procuring the First Wall Blankets that are mounted on the vacuum vessel port plugs at both the upper and equatorial levels This paper will discuss the effects of the diagnostic aperture shape and configuration on the coolant circuit design. The DFW design is driven in large part by the need to conform the coolant arrangement to a wide variety of diagnostic apertures combined with the more severe heating conditions at the surface facing the plasma, the first wall. At the first wall, a radiant heat flux of 35W/cm2 combines with approximate peak volumetric heating rates of 8W/cm3 (equatorial ports) and 5W/cm3 (upper ports). Here at the FW, a fast thermal response is desirable and leads to a thin element between the heat flux and coolant. This requirement is opposed by the wish for a thicker FW element to accommodate surface erosion and other off-normal plasma events.

G. Douglas Loesser, et. al.

2012-09-21T23:59:59.000Z

79

Predictive capabilities, analysis and experiments for Fusion Nuclear Technology, and ITER R D  

SciTech Connect (OSTI)

This report discusses the following topics on ITER research and development: trituim modeling; liquid metal blanket modeling; free surface liquid metal studies; and thermal conductance and thermal control experiments and modeling. (LIP)

Not Available

1991-01-01T23:59:59.000Z

80

Genome-Wide Identification and 3D Modeling of Proteins involved in DNA Damage Recognition and Repair (Final Report)  

SciTech Connect (OSTI)

OAK-B135 DNA Damage Recognition and Repair (DDR and R) proteins play a critical role in cellular responses to low-dose radiation and are associated with cancer. the authors have performed a systematic, genome-wide computational analysis of genomic data for human genes involved in the DDR and R process. The significant achievements of this project include: (1) Construction of the computational pipeline for searching DDR and R genes, building and validation of 3D models of proteins involved in DDR and R; (2) Functional and structural annotation of the 3D models and generation of comprehensive lists of suggested knock-out mutations; (3) Important improvement of macromolecular docking technology and its application to predict the DNA-Protein complex conformation; (4) Development of a new algorithm for improved analysis of high-density oligonucleotide arrays for gene expression profiling; (5) Construction and maintenance of the DNA Damage Recognition and Repair Database; and (6) Producing 14 research papers (10 published and 4 in preparation).

Ruben A. Abagyan, PhD

2004-04-15T23:59:59.000Z

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to obtain the most current and comprehensive results.


81

DIII-D Research in Support of ITER  

SciTech Connect (OSTI)

DIII-D research is providing key information for the design and operation of ITER. Discharges that simulate ITER operating scenarios in conventional H-mode, advanced inductive, hybrid, and steady state regimes have achieved normalized performance consistent with ITER's goals for fusion performance. Stationary discharges with high {beta}{sub N} and 90% noninductive current that project to Q=5 in ITER have been sustained for a current relaxation time ({approx}2.5 s), and high-beta wall-stabilized discharges with fully non-inductive current drive have been sustained for more than one second. Detailed issues of plasma control have been addressed, including the development of a new large-bore startup scenario for ITER. A broad research program provides the physics basis for predicting the performance of ITER. Recent key results include the discovery that the L-H power threshold is reduced with low neutral beam torque, and the development of a successful model for prediction of the H-mode pedestal height in DIII-D. Research areas with the potential to improve ITER's performance include the demonstration of ELM-free 'QH-mode' discharges with both co and counter-injection, and validation of the predicted torque generated by static, non-axisymmetric magnetic fields. New diagnostics provide detailed benchmarking of turbulent transport codes and direct measurements of the anomalous transport of fast ions by Alfven instabilities. DIII-D research also contributes to the basis for reliable operation in ITER, through active control of the chief performance-limiting instabilities. Recently, ELM suppression with resonant magnetic perturbations has been demonstrated at collisionality similar to ITER's, while simultaneous stabilization of NTMs (by localized current drive) and RWMs (by magnetic feedback) has allowed stable operation at high beta and low rotation. In research aimed at improving the lifetime of material surfaces near the plasma, recent experiments have investigated several approaches to mitigation of disruptions, including injection of low-Z gas and low-Z pellets, and have shown the conditions that minimize core impurity accumulation during radiative divertor operation. Investigation of carbon erosion, transport, and co-deposition with hydrogenic species, and methods for the removal of co-deposits, will contribute to the physics basis for initial operation of ITER with a carbon divertor.

Strait, E

2008-10-14T23:59:59.000Z

82

US ITER Project Brad Nelson  

E-Print Network [OSTI]

power supply in San Giorgio di Piano, Italy #12;FY 2014 Partner Achievements 9/23/14 FESAC ITER Progress Central Solenoid Steady State Electrical Network Tokamak Cooling Water System Toroidal Field Conductor #12 · Roughing pumps · Pellet injection · Tokamak cooling water system · Vacuum auxiliary system · Ion

83

The roadmap to magnetic confinement fusion Cutaway of the ITER tokamak. ( ITER)  

E-Print Network [OSTI]

The roadmap to magnetic confinement fusion Cutaway of the ITER tokamak. (© ITER) There are two ways breeding concepts [8] . Roadmap beyond ITER The ITER project has mapped out a road map to a commercial is the most promising for power generation (Table 2) [9] . #12;Table 2. "Fast track" fusion roadmap Facility

Hampshire, Damian

84

Michel Claessens michel.claessens@iter.org  

E-Print Network [OSTI]

the ITER Organization to continue the negotiations with the NEA (OECD Nuclear Energy Agency) in order of Environment. On 28 and 29 November 2012, the governing body of the ITER Organization convened for the first for the implementation of ITER. This will in particular allow for jointly addressing the causes of barriers to effective

85

Parent Involvement  

E-Print Network [OSTI]

To be successful, a 4-H program must have parent involvement. Although 4-H leaders and Extension agents may interest young people in becoming members, they need the parents' goodwill and support to keep them interested, enthusiastic and active. Here...

Howard, Jeff W.

2005-05-10T23:59:59.000Z

86

ITER | Princeton Plasma Physics Lab  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr FlickrGuidedCH2MLLCBasicsScience at ALCFPhysicsQualityITER

87

US ITER Moving Forward Video  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIA Energy Conference U.S. Crude OilITER Moving

88

Princeton Plasma Physics Lab - ITER  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - SeptemberMicroneedles for4-16 FOR Primary Author Last Nameenergyiter ITER is a

89

Overview of ITER ProjectOverview of ITER Project --organizational structure,organizational structure,  

E-Print Network [OSTI]

/Research Plans 3. Basic Research in support of ITER · Experimental and Theoretical Plasma Research · R

90

Iterative multiuser detection techniques for CDMA systems  

E-Print Network [OSTI]

) with (3. 40) where (ok" )' and (a&", ) are the variances of g?" and y&", ?, respectively, &t~" is the output of the inference cain:&&ll&&i in iteration n before con&bi?ing with an improved decoder input, fr&&n& the previous iteration n ? 1, denoted...

Du, Xuechao

2012-06-07T23:59:59.000Z

91

Iterative Speech Enhancement With Spectral Constraints  

E-Print Network [OSTI]

Iterative Speech Enhancement With Spectral Constraints John H. Hansen and Mark A. Clements Georgia iterative speech enhancementtechnique based on spectral constraints is presented in this paper estimate of a speech waveform in additive white noise. Thenew approach applies inter- and intra

Texas at Dallas, University of

92

Insights from US ITER: Strategies for Accelerating  

E-Print Network [OSTI]

Insights from US ITER: Strategies for Accelerating Fusion Energy as a Project Ned Sauthoff US ITER Project Manager SOFE Town Hall Meeting | June 27, 2011 #12;1. Treat fusion energy as a project, rather than a program. Mission: ·Rapid materials and fusion systems development, leading

93

ITER --"INTERNATIONAL THERMONUCLEAR EXPERIMENTAL RESEARCH PROGRAM".  

E-Print Network [OSTI]

ITER -- "INTERNATIONAL THERMONUCLEAR EXPERIMENTAL RESEARCH PROGRAM". ORGANIZATION TO DIRECT WORLD plasmas and thermonuclear burn processes (cost -$1.5-36)2. (2) An expanded, more ambitious international Thermonuclear Experimental Research Program" by L. J. Perkins #12;NORMAL-CONDUCTING COPPER OPTIONS FOR THE ITER

94

ITER11/3/04 Y. Shimomura  

E-Print Network [OSTI]

ITER11/3/04 Y. Shimomura for the ITER International and Participant Teams The 20th Fusion Energy modules Vacuum Vessel 9 sectors Cryostat 24 m high x 28 m dia. Port Plug heating/current drive test of welded plates · Vessel/Blanket ­ support arrangement simplified ­ nine lower ports ­ blanket module has

95

ITER site contest counts down Junichi Miura  

E-Print Network [OSTI]

Thermonuclear Experimental Reactor (ITER), an international project to use nuclear fusion energy for electric on a site for the project. The ITER project envisions using thermonuclear fusion to generate huge amounts heavy hydrogen and tritium used for fuel in the fusion reaction are heated in a vacuum receptacle at 100

96

IAEA-CN-SO/F-I-4 ITER: CONCEPT DEFINITION*  

E-Print Network [OSTI]

way. 1. INTRODUCTION The activity of the International Thermonuclear Experimental Reactor (ITER. * The activity of the International Thermonuclear Experimental Reactor (ITER) is conducted under the auspices

97

Annex I ITER Organization Service Contract General Conditions...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Annex I ITER Organization Service Contract General Conditions (2014) Page 1 of 21 GENERAL CONDITIONS FOR ITER ORGANIZATION SERVICE CONTRACTS (2014) Definitions...

98

Iterative Information Model Development Protein sequence  

E-Print Network [OSTI]

Protein Information Resource (PIR) Protein Science Team (11) Executive Team Members Dr. Winona Barker. Cecilia Arighi, Senior Protein Scientist, Research Assistant Professor Natalia Petrova, PhD StudentPIR Director Dr. Cathy Wu Professor PIR Director Dr. Cathy Wu Professor Bioinformatics Team (9) Executive Team

99

Dynamic simulation of a proposed ITER tritium processing system  

SciTech Connect (OSTI)

Dynamically simulating the fuel cycle in a fusion reactor is crucial to developing a better understanding of the safe and reliable operation of this complex system. In this work, we propose a tritium processing system for ITER`s plasma exhaust. The dynamic simulation of this proposed system is then performed with the TRUFFLES (TRitiUm Fusion Fuel cycLE dynamic Simulation) model. The fuel management, storage, and fueling operations are developed and coupled with previous cryopump and fuel cleanup unit subsystems to fully realize the complete torus exhaust flow cycle. Results show that tritium inventories will vary widely depending upon reactor operation, individual subsystem and unit operation designs. A diverse collection of batch-controlled subsystems with changes in their processing parameters are simulated in this work. In particular, the effects from the fuel management subsystem`s fuel reserve and tank switching times are quantified using sensitivity studies. 6 refs., 10 figs., 2 tabs.

Kuan, W.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Scott W.R. [Los Alamos National Lab., NM (United States)

1995-10-01T23:59:59.000Z

100

Value iteration for (switched) homogeneous systems  

E-Print Network [OSTI]

In this note, we prove that dynamic programming value iteration converges uniformly for discrete-time homogeneous systems and continuous-time switched homogeneous systems. For discrete-time homogeneous systems, rather than ...

Dahleh, Munther A.

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

ITERATIVE METHODS FOR NEUTRON TRANSPORT EIGENVALUE PROBLEMS  

E-Print Network [OSTI]

Abstract. We discuss iterative methods for computing criticality in nuclear reactors. In general as the inner solver. Key words. neutron transport, criticality, generalised eigenvalue problem, symmetry. Reactor criticality problems. Climate change is a challenging problem of great contemporary interest

Graham, Ivan

102

Iterated maps for clarinet-like systems  

E-Print Network [OSTI]

The dynamical equations of clarinet-like systems are known to be reducible to a non-linear iterated map within reasonable approximations. This leads to time oscillations that are represented by square signals, analogous to the Raman regime for string instruments. In this article, we study in more detail the properties of the corresponding non-linear iterations, with emphasis on the geometrical constructions that can be used to classify the various solutions (for instance with or without reed beating) as well as on the periodicity windows that occur within the chaotic region. In particular, we find a regime where period tripling occurs and examine the conditions for intermittency. We also show that, while the direct observation of the iteration function does not reveal much on the oscillation regime of the instrument, the graph of the high order iterates directly gives visible information on the oscillation regime (characterization of the number of period doubligs, chaotic behaviour, etc.).

Pierre-André Taillard; Jean Kergomard; Franck Laloë

2010-05-31T23:59:59.000Z

103

Overview of ITER Project Activities in the U.S.  

E-Print Network [OSTI]

procurement packages for bid. ­ Need to contribute team members to international ITER Organization to the ITER Organization for common expenses ­ Staff for the ITER Organization at expected US rates #12, standard components #12;Evolution of the ITER cost from $500M to $1.122B: Sum of all components ($M

104

Y.ShimomuraY.Shimomura ITER Joint Central TeamITER Joint Central Team  

E-Print Network [OSTI]

Structure #12;ICRF All metal Vacuum Transmission Line Support · Avoid dielectric material · Cool through SLIP JOINT COOLING IN COOLING OUT mm VTL GETTER PUMP #12;Mode Converter Support Structure Standard Novgorod and CRPP Lausanne ECRH/ECCD for ITER: ITER-task: Remote steering antenna for ECRH/ECCD #12

105

US Burning Plasma Workshop Oak Ridge National Laboratory US Contributions to ITER Project (US ITER)  

E-Print Network [OSTI]

US Burning Plasma Workshop Oak Ridge National Laboratory US Contributions to ITER Project (US ITER Plasma Workshop Oak Ridge, TN December 7, 2005 #12;US Burning Plasma Workshop Oak Ridge National '06 Expectations · Summary #12;US Burning Plasma Workshop Oak Ridge National Laboratory Highlights

106

JJ, IAP Cambridge January 20101 Fusion Energy & ITER:Fusion Energy & ITER  

E-Print Network [OSTI]

JJ, IAP Cambridge January 20101 Fusion Energy & ITER:Fusion Energy & ITER: Challenges Billions ITERITER startsstarts DEMODEMO decisiondecision:: Fusion impact? Energy without greenEnergy Fusion fuel: deuterium et tritium Deuterium: plenty in the ocean Tritium: made in situ from Lithium

107

A domain decomposition method of stochastic PDEs: An iterative solution techniques using a two-level scalable preconditioner  

SciTech Connect (OSTI)

Recent advances in high performance computing systems and sensing technologies motivate computational simulations with extremely high resolution models with capabilities to quantify uncertainties for credible numerical predictions. A two-level domain decomposition method is reported in this investigation to devise a linear solver for the large-scale system in the Galerkin spectral stochastic finite element method (SSFEM). In particular, a two-level scalable preconditioner is introduced in order to iteratively solve the large-scale linear system in the intrusive SSFEM using an iterative substructuring based domain decomposition solver. The implementation of the algorithm involves solving a local problem on each subdomain that constructs the local part of the preconditioner and a coarse problem that propagates information globally among the subdomains. The numerical and parallel scalabilities of the two-level preconditioner are contrasted with the previously developed one-level preconditioner for two-dimensional flow through porous media and elasticity problems with spatially varying non-Gaussian material properties. A distributed implementation of the parallel algorithm is carried out using MPI and PETSc parallel libraries. The scalabilities of the algorithm are investigated in a Linux cluster.

Subber, Waad, E-mail: wsubber@connect.carleton.ca; Sarkar, Abhijit, E-mail: abhijit_sarkar@carleton.ca

2014-01-15T23:59:59.000Z

108

San Diego 01.05.2001 Power and Particle Exhaust in ITER Slide 1 by G. Janeschitz, et.al. _______________________________________________________________________ ITER  

E-Print Network [OSTI]

San Diego 01.05.2001 Power and Particle Exhaust in ITER Slide 1 by G. Janeschitz, et.al. ITER Exhaust in ITER Slide 2 by G. Janeschitz. ITER to pump #12;San Diego; 01.05.2001 Power and Particle Exhaust in ITER Slide 3 by G. Janeschitz. ITER

109

ITER risk workshop participant guide  

SciTech Connect (OSTI)

The goal of planning risk management is to make everyone involved in a program aware that risk should be a consideration in the design, development, and fielding of a system. Risk planning is a tool to assess and mitigate events that might adversely impact the program. Therefore, risk management increases the probability/likelihood of program success and can help to avoid program crisis management and improve problem solving by managing risk early in the acquisition cycle.

Medina, Patricia [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

110

US solid breeder blanket design for ITER  

SciTech Connect (OSTI)

The US blanket design activity has focused on the developments and the analyses of a solid breeder blanket concept for ITER. The main function of this blanket is to produce the necessary tritium required for the ITER operation and the test program. Safety, power reactor relevance, low tritium inventory, and design flexibility are the main reasons for the blanket selection. The blanket is designed to operate satisfactorily in the physics and the technology phases of ITER without the need for hardware changes. Mechanical simplicity, predictability, performance, minimum cost, and minimum R D requirements are the other criteria used to guide the design process. The design aspects of the blanket are summarized in this paper. 2 refs., 7 figs., 3 tabs.

Gohar, Y.; Attaya, H.; Billone, M.; Lin, C.; Johnson, C.; Majumdar, S.; Smith, D. (Argonne National Lab., IL (USA)); Goranson, P.; Nelson, B.; Williamson, D.; Baker, C. (Oak Ridge National Lab., TN (USA)); Raffray, A.; Badawi, A.; Gorbis, Z.; Ying, A.; Abdou, M. (California Univ., Los Angeles, CA (USA)); Sviatoslavsky, I.; Blanchard, J.; Mogahed, E.; Sawan, M.; Kulcinski, G. (Wisconsin Univ., Madison, WI (USA))

1990-09-01T23:59:59.000Z

111

Pellet Fueling Technology Development Leading to Efficient Fueling of ITER Burning Plasmas  

SciTech Connect (OSTI)

Pellet injection is the primary fueling technique planned for central fueling of the ITER burning plasma, which is a requirement for achieving high fusion gain. Injection of pellets from the inner wall has been shown on present day tokamaks to provide efficient fueling and is planned for use on ITER [1,2]. Significant development of pellet fueling technology has occurred as a result of the ITER R&D process. Extrusion rates with batch extruders have reached more than 1/2 of the ITER design specification of 1.3 cm3/s [3] and the ability to fuel efficiently from the inner wall by injecting through curved guide tubes has been demonstrated on several fusion devices. Modeling of the fueling deposition from inner wall pellet injection has been done using the Parks et al. ExB drift model [4] shows that inside launched pellets of 3mm size and speeds of 300 m/s have the capability to fuel well inside the separatrix. Gas fueling on the other hand is calculated to have very poor fueling efficiency due to the high density and wide scrape off layer compared to current machines. Isotopically mixed D/T pellets can provide efficient tritium fueling that will minimize tritium wall loading when compared to gas puffing of tritium. In addition, the use of pellets as an ELM trigger has been demonstrated and continues to be investigated as an ELM mitigation technique. During the ITER CDA and EDA the U.S. was responsible for ITER fueling system design and R&D and is in good position to resume this role for the ITER pellet fueling system. Currently the performance of the ITER guide tube design is under investigation. A mockup is being built that will allow tests with different pellet sizes and repetition rates. The results of these tests and their implication for fueling efficiency and central fueling will be discussed. The ITER pellet injection technology developments to date, specified requirements, and remaining development issues will be presented along with a plan to reach the design goal in time for employment on ITER.

Baylor, Larry R [ORNL; Combs, Stephen Kirk [ORNL; Jernigan, Thomas C [ORNL; Houlberg, Wayne A [ORNL; Maruyama, S. [ITER International Team, Garching, Germany; Owen, Larry W [ORNL; Parks, P. B. [General Atomics; Rasmussen, David A [ORNL

2005-01-01T23:59:59.000Z

112

Beyond ITER: Neutral beams for DEMO  

E-Print Network [OSTI]

In the development of magnetically confined fusion as an economically sustainable power source, ITER is currently under construction. Beyond ITER is the DEMO programme in which the physics and engineering aspects of a future fusion power plant will be demonstrated. DEMO will produce net electrical power. The DEMO programme will be outlined and the role of neutral beams for heating and current drive will be described. In particular, the importance of the efficiency of neutral beam systems in terms of injected neutral beam power compared to wallplug power will be discussed. Options for improving this efficiency including advanced neutralisers and energy recovery are discussed.

McAdams, R

2013-01-01T23:59:59.000Z

113

Plan and Strategy for ITER Blanket Testing in Japan  

SciTech Connect (OSTI)

The Fusion Council of Japan has established the long-term program for the development of blanket in 1999. In the program, the solid breeder blanket was selected as the primary candidate blanket of the fusion power demonstration plant in Japan, while liquid breeder blankets and high temperature solid breeder blanket have been identified as the attractive advanced blanket. Japan Atomic Energy Research Institute (JAERI) is leading the development of solid breeder blankets, while, universities and National Institute for Fusion Science (NIFS) are developing the advanced blankets for potential options of the fusion power demonstration plant and commercial power plants. ITER blanket module testing is regarded as one of the most important milestones, by which integrity of candidate blanket design is qualified for the fusion power demonstration plant, together with material irradiation data by International Fusion Material Irradiation Facility (IFMIF). Japan is investigating the possibility of testing all types of blankets under TBWG framework with both of JAERI and universities/NIFS involvements. This paper presents a plan and strategy for the development of test blanket modules and ITER blanket module testing in Japan.

Enoeda, Mikio [Japan Atomic Energy Research Institute (Japan); Akiba, Masato [Japan Atomic Energy Research Institute (Japan); Tanaka, Satoru [University of Tokyo (Japan); Shimizu, Akihiko [Kyushu University (Japan); Hasegawa, Akira [Tohoku University (Japan); Konishi, Satoshi [Kyoto University (Japan); Kimura, Akihiko [Kyoto University (Japan); Kohyama, Akira [Kyoto University (Japan); Sagara, Akio [National Institute of Fusion Science (Japan); Muroga, Takeo [National Institute of Fusion Science (Japan)

2005-05-15T23:59:59.000Z

114

Parallel computation of multigroup reactivity coefficient using iterative method  

SciTech Connect (OSTI)

One of the research activities to support the commercial radioisotope production program is a safety research target irradiation FPM (Fission Product Molybdenum). FPM targets form a tube made of stainless steel in which the nuclear degrees of superimposed high-enriched uranium. FPM irradiation tube is intended to obtain fission. The fission material widely used in the form of kits in the world of nuclear medicine. Irradiation FPM tube reactor core would interfere with performance. One of the disorders comes from changes in flux or reactivity. It is necessary to study a method for calculating safety terrace ongoing configuration changes during the life of the reactor, making the code faster became an absolute necessity. Neutron safety margin for the research reactor can be reused without modification to the calculation of the reactivity of the reactor, so that is an advantage of using perturbation method. The criticality and flux in multigroup diffusion model was calculate at various irradiation positions in some uranium content. This model has a complex computation. Several parallel algorithms with iterative method have been developed for the sparse and big matrix solution. The Black-Red Gauss Seidel Iteration and the power iteration parallel method can be used to solve multigroup diffusion equation system and calculated the criticality and reactivity coeficient. This research was developed code for reactivity calculation which used one of safety analysis with parallel processing. It can be done more quickly and efficiently by utilizing the parallel processing in the multicore computer. This code was applied for the safety limits calculation of irradiated targets FPM with increment Uranium.

Susmikanti, Mike [Center for Development of Nuclear Informatics, National Nuclear Energy Agency of Indonesia PUSPIPTEK Area, Tangerang (Indonesia)] [Center for Development of Nuclear Informatics, National Nuclear Energy Agency of Indonesia PUSPIPTEK Area, Tangerang (Indonesia); Dewayatna, Winter [Center for Nuclear Fuel Technology, National Nuclear Energy Agency of Indonesia PUSPIPTEK Area, Tangerang (Indonesia)] [Center for Nuclear Fuel Technology, National Nuclear Energy Agency of Indonesia PUSPIPTEK Area, Tangerang (Indonesia)

2013-09-09T23:59:59.000Z

115

Michel Claessens michel.claessens@iter.org  

E-Print Network [OSTI]

's recommendations. The ITER Council also approved two important technical proposals that will have a positive impact of research and development on the tungsten divertor that was supported by successful experiments and testing Tokamak JET (UK). Council also noted the progress on the design and prototype development of the in

116

ITER Project Status Fusion Energy Sciences  

E-Print Network [OSTI]

. Manufacturing of an ITER vacuum vessel segment in Korea 04/09/14 FESAC/Sauthoff 12 (Photos: KO DA) #12;Russia to capped value) ORNL 100% Tokamak Cooling Water System PPPL 75% Steady State Electrical Network PPPL 14 tooling stations #12;Central Solenoid Specs: 6 independent coil packs of cable-in- conduit conductor

117

CONTRACTIVITY IN TURBO ITERATIONS Phillip A. Regalia  

E-Print Network [OSTI]

CONTRACTIVITY IN TURBO ITERATIONS Phillip A. Regalia Department of Communications, Image Fourier 91011 Evry cedex France Phillip.Regalia@int-evry.fr ABSTRACT The turbo decoding algorithm has met with intense study over the past decade, in an attempt to harness the full power of the "turbo principle". Here

Regalia, Phillip A.

118

Limited View Angle Iterative CT Reconstruction  

E-Print Network [OSTI]

;Some Prior Literature in Limited View Tomography CT with limited-angle data and few views IRR algorithm Iterative Reconstruction-Reprojection (IRR) : An Algorithm for Limited Data Cardiac- Computed-views and limited-angle data in divergent-beam CT by E. Y. Sidky, CM Kao, and X. Pan (2006) Few-View Projection

119

Funding for nuclear fusion Expensive Iteration  

E-Print Network [OSTI]

producing more energy than is put in. The International Thermonuclear Experimental Reactor became plain ITER aims to produce energy by fusing together the nuclei of hydrogen atoms, confined in a magnetic field. Initial projections in 2006 put its price at 10 billion ($13 billion): 5 billion to build and another 5

120

Bold Step by the World to Fusion Energy: ITER  

E-Print Network [OSTI]

THE DESIGN OF ITER · ITER PROJECT & ROLE OF THE UNITED STATES · PATH FROM ITER TO PRACTICAL FUSION POWER #12;Elements of a D-T Fusion Energy System ~ D-Li Plasma Heating Drivers or Confinement Balance of PlantD = nT = n TOTAL THERMAL ENERGY IN FUSION FUEL, DEFINE "ENERGY CONFINEMENT TIME", E ENERGY BALANCE dW d

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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121

CCFE-PR(13)44 Beyond ITER: Neutral beams  

E-Print Network [OSTI]

R. McAdams CCFE-PR(13)44 Beyond ITER: Neutral beams for DEMO #12;Enquiries about copyright Kingdom Atomic Energy Authority is the copyright holder. #12;Beyond ITER: Neutral beams for DEMO R. Mc ITER: Neutral beams for DEMOa) R. McAdamsb) EURATOM/CCFE Association, Culham Science Centre, Abingdon

122

ITER HEAT REMOVAL SYSTEM SYSTEM & PROCESS CONTROL DESIGN  

E-Print Network [OSTI]

normal pulse operation, the heat deposited in the in-vessel components is released into the environment. Ito 1 , P. Lorenzetto 4 , Y. Okawa 5 1 ITER Joint Central Team, 11025 North Torrey Pines Road, La Jolla, CA, 92037, USA; 2 ITER Joint Central Team, Naka, Japan; 3 ITER Joint Central Team, Garching

Raffray, A. René

123

A Conditional Logic for Iterated Belief Revision Laura Giordano  

E-Print Network [OSTI]

A Conditional Logic for Iterated Belief Revision Laura Giordano DSTA ­ Universitâ?? a del Piemonte Abstract. In this paper we propose a conditional logic IBC to rep­ resent iterated belief revision. We define an iterated belief revision system by strengthening the postulates proposed by Darwiche and Pearl

Giordano, Laura

124

Simulations of Alpha Wall Load in ITER. Final report  

SciTech Connect (OSTI)

The partially DOE funded International Thermonuclear Experimental Reactor (ITER) will produce massive amounts of energetic charged alpha particles, which are imperfectly confined by a strong magnetic field. The wall of the experiment is designed to withstand an estimated wall load from these fusion alpha particles, but the accuracy of this estimate needs to be improved to avoid potentially catastrophic surprises when the experiment becomes operational. We have added a more accurate, gyro-dynamic model of particle motion to the existing drift-dynamic model in the DELTA5D simulation software used for the project. We have also added the ability to load a detailed engineering model of the wall and use it in the simulations.

Carlsson, Johan

2010-10-20T23:59:59.000Z

125

on the Establishment of the ITER International Fusion Energy Organization for the Joint Implementation of the ITER Project  

E-Print Network [OSTI]

AGREEMENT on the Establishment of the ITER International Fusion Energy Organization for the Joint Fusion Energy Organization Article 2 Purpose of the ITER Organization Article 3 Functions of the ITER://fusionforenergy.europa.eu/downloads/aboutf4e/l_35820061216en00620081.pdf #12;Preamble The European Atomic Energy Community (hereinafter

126

HEART SEGMENTATION WITH AN ITERATIVE CHAN-VESE OLIVIER ROUSSEAU, YVES BOURGAULT  

E-Print Network [OSTI]

HEART SEGMENTATION WITH AN ITERATIVE CHAN-VESE ALGORITHM OLIVIER ROUSSEAU, YVES BOURGAULT Abstract. This paper presents 2D and 3D applications of the Chan-Vese model to heart and trachea segmentation. We is to segment the heart muscle from high resolution CT scans of the thorax and to produce meshes

Paris-Sud XI, Université de

127

Commitment to Public Involvement  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Create a Sustainable Future Commitment to Public Involvement Commitment to Public Involvement LANL is commited to our neighbors August 1, 2013 Lab Director McMillan talks with...

128

Thermomechanical analysis of the ITER breeding blanket  

SciTech Connect (OSTI)

Thermomechanical performance of the ITER breeding blanket is an important design issue because it requires first, that the thermal expansion mismatch between the blanket structure and the blankets internals (such as, beryllium multiplier and tritium breeders) can be accommodated without creating high stresses, and second, that the thermomechanical deformation of various interfaces within the blanket does not create high resistance to heat flow and consequent unacceptably high temperatures in the blanket materials. Thermomechanical analysis of a single beryllium block sandwiched between two stainless steel plates was carried out using the finite element code ABAQUS to illustrate the importance of elastic deformation on the temperature distributions. Such an analysis for the whole ITER blanket needs to be conducted in the future. Uncertainties in the thermomechanical contact analysis can be reduced by bonding the beryllium blocks to the stainless steel plates by a thin soft interfacial layer.

Majumdar, S.; Gruhn, H. [Argonne National Lab., IL (United States); Gohar, Y.; Giegerich, M. [Max-Planck-Institut fuer Plasmaphysik, Muenchen (Germany). ITER Joint Central Team

1997-03-01T23:59:59.000Z

129

ITER Physics and Exploring Magnetically-Confined  

E-Print Network [OSTI]

the Scientific and Technological Feasibility of Fusion Energy for Peaceful Purposes #12;Special ITER Features???Flow/rotation Port-based coils?RWM Stab. x~1.9, 95%~1.7 x~0.5, 95%~0.33 Shaping J(0)Jefficient (r>a/2)J (R)J(0) ­ pedestal characteristics ­ core-edge integration ­ ITB-access at low- * with weak rotation · Demands

130

US Demo test blankets in ITER  

SciTech Connect (OSTI)

This paper summarizes the current status of the Demo blanket test systems and how the ITER reactor design and operations are being accommodated. The US blanket program is planning to develop a liquid metal breeder and a solid breeder blanket for testing and evaluation. The test blanket modules will have prototypical components, materials, and coolants representative of power reactor systems. The modules are to be located in the ITER horizontal test ports and installed/removed with special remote handling equipment. Adjacent ITER blanket neutronic and temperature conditions suggest the use of an isolation frame surrounding the test blanket modules or submodules. This frame will also provide additional shielding to protect the adjacent vacuum vessel. The frame and blanket module are attached to the surrounding backplate to transfer static and dynamic loads. All coolants and tritium-bearing fluids will be routed out of the midplane port to special heat exchangers and tritium separation systems. Special remote handling equipment is being designed to install and extract the test blanket modules. Dedicated transporters will be used to move the blanket and shielding modules to dedicated hot cells. Special facility areas will be provided immediately outside the port areas for the heat exchangers, pumps, and tritium-separation systems. 1 ref., 6 figs.

Waganer, L.M.; Lee, V.D [McDonnell Douglas Aerospace, St. Louis, MO (United States); Abdou, M.A.; Ying, A.Y. [Univ. of California, Los Angeles, CA (United States); Hua, T.; Sze, D.K. [Argonne National Lab., IL (United States); Dagher, M.A. [Rockwell International Corp., Canoga Park, CA (United States)

1996-12-31T23:59:59.000Z

131

Occupational Radiation Exposure Analysis of US ITER DCLL TBM  

SciTech Connect (OSTI)

This report documents an Occupational Radiation Exposure (ORE) analysis that was performed for the US International Thermonuclear Experimental Reactor (ITER) Dual Coolant Lead Lithium (DCLL) Test Blanket Module (TBM). This analysis was performed with the QADMOD dose code for anticipated maintenance activities for this TBM concept and its ancillary systems. The QADMOD code was used to model the PbLi cooling loop of this TBM concept by specifying gamma ray source terms that simulated radioactive material within the piping, valves, heat exchanger, permeator, pump, drain tank, and cold trap of this cooling system. Estimates of the maintenance tasks that will have to be performed and the time required to perform these tasks where developed based on either expert opinion or on industrial maintenance experience for similar technologies. This report details the modeling activity and the calculated doses for the maintenance activities envisioned for the US DCLL TBM.

Merrill, Brad J; Cadwallader, Lee C; Dagher, Mohamad

2007-08-01T23:59:59.000Z

132

An iterative technique for solving equations of statistical equilibrium  

E-Print Network [OSTI]

Superlevel partitioning is combined with a simple relaxation procedure to construct an iterative technique for solving equations of statistical equilibrium. In treating an $N$-level model atom, the technique avoids the $N^{3}$ scaling in computer time for direct solutions with standard linear equation routines and also does not fail at large $N$ due to the accumulation of round-off errors. In consequence, the technique allows detailed model atoms with $N \\ga 10^{3}$, such as those required for iron peak elements, to be incorporated into diagnostic codes for analysing astronomical spectra. Tests are reported for a 394-level Fe II ion and a 1266-level Ni I--IV atom.

L. B. Lucy

2001-03-21T23:59:59.000Z

133

Development and test of the ITER conductor joints  

SciTech Connect (OSTI)

Joints for the ITER superconducting Central Solenoid should perform in rapidly varying magnetic field with low losses and low DC resistance. This paper describes the design of the ITER joint and presents its assembly process. Two joints were built and tested at the PTF facility at MIT. Test results are presented, losses in transverse and parallel field and the DC performance are discussed. The developed joint demonstrates sufficient margin for baseline ITER operating scenarios.

Martovetsky, N., LLNL

1998-05-14T23:59:59.000Z

134

Variational Iteration Method for Image Restoration  

E-Print Network [OSTI]

The famous Perona-Malik (P-M) equation which was at first introduced for image restoration has been solved via various numerical methods. In this paper we will solve it for the first time via applying a new numerical method called the Variational Iteration Method (VIM) and the correspondent approximated solutions will be obtained for the P-M equation with regards to relevant error analysis. Through implementation of our algorithm we will access some effective results which are deserved to be considered as worthy as the other solutions issued by the other methods.

Yahya, Keyvan; Azari, Hossein; Fard, Pouyan Rafiei

2010-01-01T23:59:59.000Z

135

US ITER toroidal field coil conductor produc  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof EnergyLeaseEnergyUNCLASSIFIED ITER toroidal field

136

p-points in iterated forcing extensions  

E-Print Network [OSTI]

Ma. By Fact 4, U aiterated ccc extensions whose length has uncountable cofinality. These theorems are proved in §3. In §4 we indicate how...

Roitman, Judith A.

1978-05-03T23:59:59.000Z

137

Y.ShimomuraY.Shimomura ITER Joint Central TeamITER Joint Central Team  

E-Print Network [OSTI]

mobility between ITER and domestic programmes #12;Reactor Development: Stable fusion power production;0 0.2 0.4 0.6 0.8 1 0 0.5 1 1.5 2 2.5 3 3.5 Vp, km/s 11 12 13 14 23 21 22 X HFS pellet speed ~ 300 m

138

TRANSP Tests Of TGLF and Predictions For ITER  

SciTech Connect (OSTI)

Gyro kinetic simulations of turbulence capture some of the features observed in transport, fluctuations, and correlations measured in tokamak plasmas. These codes calculations are CPU intensive, and are not practical for incorporation in present time-dependant transport codes, so reduced models based on these gyro kinetic codes are being used. An example is the TGLF model [1] which is a quasilinear gyrofluid model calibrated to nonlinear results from the GYRO code [2]. Recently TGLF has been incorporated into TRANSP. Analysis of experimental data using TRANSP with such models provides fundamental understanding of turbulent transport. Predictions of ITER performance with various plasma scenarios using such models are useful for optimizing design and for exposing issues that can be addressed in present experiments and theory. For instance, which combinations of heating, torquing, and current drive are optimal. Another application is for nuclear licensing (e.g. system integrity, neutron rates). Others are generating inputs for design of diagnostic systems and for theoretical studies. An example of the later is Alfv´en Eigenmode and AE-induced loss of fast ions. The beam ion distribution can either enhance or reduce the alpha pressure drive of the AE instability. The AE instability can cause dangerous amounts of fast ion losses, as was seen in TFTR.

none,; Budny, Robert; Yuan, Xingqiu

2014-02-26T23:59:59.000Z

139

A review of ITER blanket designs  

SciTech Connect (OSTI)

Changes in ITER requirements and conditions in the Engineering Design Activity (EDA), and the desire to obtain greater operating flexibility, led to a reconsideration of the ITER Conceptual Design Activity (CDA) blanket designs. The current strategy is to follow a two-tiered development approach: The reference design blanket is non-breeding, and satisfies only the basic performance phase (BPP) functional requirements. This blanket would need to be changed out for the extended performance (EPP). A lower level development effort is also underway on a tritium-breeding blanket. The decision as to which of the two designs to adopt will be made at the end of a two-year development effort. This paper describes the present candidate blankets and the issues associated with each of them. The reference design is a non-breeding, low temperature, low pressure, water cooled, austenitic stainless steel (316SS) blanket/shield (BS). The first wall (FW), which may be integral with or separate from the BS, is a bonded copper-alloy/SS structure with a beryllium coating. Critical issues here are copper-SS bonding, fabricability, and radiation damage and stress corrosion cracking of the SS. The breeding blanket utilizes vanadium alloy structural material, with lithium as the breeder. The coolants are either lithium (self-cooled) or high pressure helium. The primary issues here are the need to electrically insulate the flow channels, the qualification of vanadium as a structural material, and the fabrication of large vanadium structures.

Green, L.; Carelli, M.D.; Stefani, F. [Westinghouse Science & Technology Center, Pittsburgh, PA (United States); Morgan, G.D. [McDonnell Douglas Corp., St. Louis, MO (United States); Mattas, R. [Argonne National Lab., IL (United States)

1994-11-01T23:59:59.000Z

140

Diverse Power Iteration Embeddings and Its Applications  

SciTech Connect (OSTI)

Abstract—Spectral Embedding is one of the most effective dimension reduction algorithms in data mining. However, its computation complexity has to be mitigated in order to apply it for real-world large scale data analysis. Many researches have been focusing on developing approximate spectral embeddings which are more efficient, but meanwhile far less effective. This paper proposes Diverse Power Iteration Embeddings (DPIE), which not only retains the similar efficiency of power iteration methods but also produces a series of diverse and more effective embedding vectors. We test this novel method by applying it to various data mining applications (e.g. clustering, anomaly detection and feature selection) and evaluating their performance improvements. The experimental results show our proposed DPIE is more effective than popular spectral approximation methods, and obtains the similar quality of classic spectral embedding derived from eigen-decompositions. Moreover it is extremely fast on big data applications. For example in terms of clustering result, DPIE achieves as good as 95% of classic spectral clustering on the complex datasets but 4000+ times faster in limited memory environment.

Huang H.; Yoo S.; Yu, D.; Qin, H.

2014-12-14T23:59:59.000Z

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Edge plasma studies for ITER and related B2 code development  

SciTech Connect (OSTI)

During the past three years the B2 code has been entirely re-written. This contract report will serve as a provisional user guide for the new (B2.5) code, which is hereby made available to the ITER modellers. A definitive description of the new code will be prepared in the course of the present year. The following changes to the physics (with respect to the B2 code version now in wide use) should be noted. The representation of the atomic physics now relies on rate coefficients obtained from either of two code packages: the ADPAK collection developed by R. A. Hulse of Princeton PPL and the STRAHL collection developed by K. Behringer of Garching and JET. These are used to prepare tables of rate coefficients for ionization, recombination, radiation, and charge exchange, involving hydrogen and any impurities that are of interest. A fluid model is now available to describe the neutral species. The neutral fluid is governed by a convection-diffusion equation of similar form as all the other equations solved in the code; the diffusivity is based on the thermal velocity and the mean free path for ionization and charge exchange. The code has been extensively modified in the interest of clarity of design and ease of use. The internal documentation has been expanded, so that almost all variables are now clearly described and every small segment of code has a clearly stated purpose. Some steps were made toward including a full treatment of the electric potential and of diamagnetic transport. The poloidal transport is no longer tied to the parallel transport by a simple factor B[sub [theta

Weitzner, H.; Braams, B.

1992-03-01T23:59:59.000Z

142

Edge plasma studies for ITER and related B2 code development  

SciTech Connect (OSTI)

During the past three years the B2 code has been entirely re-written. This contract report will serve as a provisional user guide for the new (B2.5) code, which is hereby made available to the ITER modellers. A definitive description of the new code will be prepared in the course of the present year. The following changes to the physics (with respect to the B2 code version now in wide use) should be noted. The representation of the atomic physics now relies on rate coefficients obtained from either of two code packages: the ADPAK collection developed by R. A. Hulse of Princeton PPL and the STRAHL collection developed by K. Behringer of Garching and JET. These are used to prepare tables of rate coefficients for ionization, recombination, radiation, and charge exchange, involving hydrogen and any impurities that are of interest. A fluid model is now available to describe the neutral species. The neutral fluid is governed by a convection-diffusion equation of similar form as all the other equations solved in the code; the diffusivity is based on the thermal velocity and the mean free path for ionization and charge exchange. The code has been extensively modified in the interest of clarity of design and ease of use. The internal documentation has been expanded, so that almost all variables are now clearly described and every small segment of code has a clearly stated purpose. Some steps were made toward including a full treatment of the electric potential and of diamagnetic transport. The poloidal transport is no longer tied to the parallel transport by a simple factor B{sub {theta}}/B, but includes diffusive contributions. A two-dimensional elliptic equation is solved to obtain the electric potential, assuming an anomalous cross-field resistivity and thermo-electric coefficient of the plasma.

Weitzner, H.; Braams, B.

1992-03-01T23:59:59.000Z

143

Involvement and Communication Committee.  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Public Involvement and Communication Committee Chair 1 : Liz Mattson 4 , Alternate Vice Chair 1 : Ken Niles 4 , Member Committee Members 2 : Shelley Cimon Peggy Maze Johnson Rob...

144

Proving termination by policy iteration Damien Masse1  

E-Print Network [OSTI]

NSAD 2012 Proving termination by policy iteration Damien Mass´e1 Lab-Sticc, UMR 6285 UBO conditions for program termination. Restricting ourselves to affine programs and the abstract domain. Keywords: Abstract interpretation, policy iteration, template constraint matrices, termination analysis. 1

Paris-Sud XI, Université de

145

October 6, 1997 ITER L-Mode Con nement Database  

E-Print Network [OSTI]

October 6, 1997 ITER L-Mode Con nement Database S.M. Kaye and the ITER Con nement Database Working Group Abstract This paper describes the content of an L-mode database that has been compiled with data, and Tore-Supra. The database consists of a total of 2938 entries, 1881 of which are in the L-phase while

146

A Turbo Iteration Algorithm In 16QAM Hierarchical Modulation  

E-Print Network [OSTI]

A Turbo Iteration Algorithm In 16QAM Hierarchical Modulation Xu Zhe Electric and Information on the turbo code, OFDM modulation and 16QAM hierarchical modulation to increase the flexibility, and in the high SNR, it can also gain a high BER performance of low priority bit stream. Keywords- turbo iteration

Paris-Sud XI, Université de

147

Properties of Iterated Multiple Belief Revision Dongmo Zhang  

E-Print Network [OSTI]

in the community of belief revision[2][5][9][10][13][17]. The major concern in the research is the reducibilityProperties of Iterated Multiple Belief Revision Dongmo Zhang School of Computing and Information investigate the properties of iterated multiple belief revision. We examine several typical assumptions

Zhang, Dongmo

148

Iterated Belief Revision and Conditional Logic Laura Giordano  

E-Print Network [OSTI]

/01/2001; 17:22; p.1 #12; 2 well known Triviality Result [5], that claims that no signi#12;cant belief revisionIterated Belief Revision and Conditional Logic Laura Giordano DSTA - Universit#18;a del Piemonte a conditional logic called IBC to represent iterated belief revision systems. We propose a set of postulates

Torino, Università di

149

BLIND ITERATIVE RESTORATION OF IMAGES WITH SPATIALLY-VARYING BLUR  

E-Print Network [OSTI]

BLIND ITERATIVE RESTORATION OF IMAGES WITH SPATIALLY-VARYING BLUR John Bardsley Stuart Jefferies (PSF) by using a combination of methods including sectioning and phase diversity blind deconvolution whose PSFs are correlated and approximately spatially-invariant, and apply iterative blind deconvolution

Bardsley, John

150

ITER CENTRAL SOLENOID COIL INSULATION QUALIFICATION  

SciTech Connect (OSTI)

An insulation system for ITER Central Solenoid must have sufficiently high electrical and structural strength. Design efforts to bring stresses in the turn and layer insulation within allowables failed. It turned out to be impossible to eliminate high local tensile stresses in the winding pack. When high local stresses can not be designed out, the qualification procedure requires verification of the acceptable structural and electrical strength by testing. We built two 4 x 4 arrays of the conductor jacket with two options of the CS insulation and subjected the arrays to 1.2 million compressive cycles at 60 MPa and at 76 K. Such conditions simulated stresses in the CS insulation. We performed voltage withstand tests and after end of cycling we measured the breakdown voltages between in the arrays. After that we dissectioned the arrays and studied micro cracks in the insulation. We report details of the specimens preparation, test procedures and test results.

Martovetsky, N N; Mann, T L; Miller, J R; Freudenberg, K D; Reed, R P; Walsh, R P; McColskey, J D; Evans, D

2009-06-11T23:59:59.000Z

151

ITER L-Mode Confinement Database  

SciTech Connect (OSTI)

This paper describes the content of an L-mode database that has been compiled with data from Alcator C-Mod, ASDEX, DIII, DIII-D, FTU, JET, JFT-2M, JT-60, PBX-M, PDX, T-10, TEXTOR, TFTR, and Tore-Supra. The database consists of a total of 2938 entries, 1881 of which are in the L-phase while 922 are ohmically heated (OH) only. Each entry contains up to 95 descriptive parameters, including global and kinetic information, machine conditioning, and configuration. The paper presents a description of the database and the variables contained therein, and it also presents global and thermal scalings along with predictions for ITER. The L-mode thermal confinement time scaling was determined from a subset of 1312 entries for which the thermal confinement time scaling was provided.

S.M. Kaye and the ITER Confinement Database Working Group

1997-10-01T23:59:59.000Z

152

ITER Central Solenoid Coil Insulation Qualification  

SciTech Connect (OSTI)

An insulation system for ITER Central Solenoid must have sufficiently high electrical and structural strength. Design efforts to bring stresses in the turn and layer insulation within allowables failed. It turned out to be impossible to eliminate high local tensile stresses in the winding pack. When high local stresses can not be designed out, the qualification procedure requires verification of the acceptable structural and electrical strength by testing. We built two 4x4 arrays of the conductor jacket with two options of the CS insulation and subjected the arrays to 1.2 million compressive cycles at 60 MPa and at 76 K. Such conditions simulated stresses in the CS insulation. We performed voltage withstand tests and after end of cycling we measured the breakdown voltages between in the arrays. After that we dissectioned the arrays and studied micro cracks in the insulation. We report details of the specimens preparation, test procedures and test results.

Martovetsky, Nicolai N [ORNL] [ORNL; Mann Jr, Thomas Latta [ORNL] [ORNL; Miller, John L [ORNL] [ORNL; Freudenberg, Kevin D [ORNL] [ORNL; Reed, Richard P [Cryogenic Materials, Inc.] [Cryogenic Materials, Inc.; Walsh, Robert P [Florida State University] [Florida State University; McColskey, J D [National Institute of Standards and Technology (NIST), Boulder] [National Institute of Standards and Technology (NIST), Boulder; Evans, D [Advanced Cryogenic Materials] [Advanced Cryogenic Materials

2010-01-01T23:59:59.000Z

153

Intense Diagnostic Neutral Beam for ITER LANL-Park and Wurden Intense Diagnostic Neutral Beam for ITER  

E-Print Network [OSTI]

for ITER Jaeyoung Park and Glen A. Wurden Plasma Physics Group (P-24) Los Alamos National Laboratory LosIntense Diagnostic Neutral Beam for ITER LANL-Park and Wurden 2 Intense Diagnostic Neutral Beam Alamos, NM 87545 Executive Summary An intense pulsed diagnostic neutral beam (IDNB) is proposed to enable

154

Radioactivity measurements of ITER materials using TFTR D-T neutron field  

SciTech Connect (OSTI)

TFTR successfully initiated trace tritium plasma experiments in mid-November 1993. During the coming year, the TFTR plasma tritium fraction is scheduled to be increased to at least 50%. The availability of larger amounts of D-T fusion neutrons in the high power D-T plasma phase of TFTR provides an useful opportunity to directly measure D-T neutron induced radioactivity in a realistic tokamak-environment in materials of vital interest to ITER. These measurements are invaluable for characterizing short and long lived radioactivity in various ITER candidate materials, for validating complex neutron transport calculations, and for meeting fusion reactor licensing requirements. The radioactivity measurements at TFTR will involve potential ITER materials that include stainless steel 316, vanadium-alloy, copper, iron, nickel, chromium, vanadium, titanium, manganese, cobalt, molybdenum, zinc, niobium, zirconium, tungsten, lead, tin, silicon, etc. Small samples of these materials will be irradiated in varying neutron energy spectra at the vacuum vessel first wall. These irradiated samples will then be counted for {gamma}-radioactivity at different cooling times to get extensive information on as many {gamma}-emitting radioactive products as feasible.

Kumar, A.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Kugel, H.W. [Princeton Univ., NJ (United States)] [and others

1994-12-31T23:59:59.000Z

155

The development of iterative and cascade methods for the rapid synthesis of ladder polyether natural products  

E-Print Network [OSTI]

I. The Development of Methods for the Iterative Synthesis of Polytetrahydropyrans An iterative method comprising chain homologation, epoxidation, 6-endo cyclization, and protiodesilylation was developed. Notable achievements ...

Heffron, Timothy Paul

2005-01-01T23:59:59.000Z

156

Atomic data for the ITER Core Imaging X-ray Spectrometer  

SciTech Connect (OSTI)

The parameters of the ITER core plasmas will be measured using the Core Imaging X-ray Spectrometer (CIXS), a high-resolution crystal spectrometer focusing on the L-shell spectra of highly ionized tungsten atoms. In order to correctly infer the plasma properties accurate atomic data are required. Here, some aspects of the underlying physics are discussed using experimental data and theoretical predictions from modeling.

Clementson, J; Beiersdorfer, P; Biedermann, C; Bitter, M; Delgado-Aparicio, L F; Graf, A; Gu, M F; Hill, K W; Barnsley, R

2012-06-15T23:59:59.000Z

157

Information Technology Systems for Fusion Industry and ITER Project  

SciTech Connect (OSTI)

The industrial developments in the fusion industry will have to overcome numerous technical challenges and will have a strong need for modern information technology (IT) systems.The fusion industry has manifested itself with an unprecedented international collaboration, the International Thermonuclear Experimental Reactor (ITER). Data accumulated in ITER will be the major output of the project and will create the knowledge base for a future fusion power plant. A modern and effective information infrastructure will be critical to the success of the ITER project.To accumulate and maintain the knowledge base at all stages of the project, we propose to build an integrated information system for ITER: ITER Information Plant (IIP). IIP will minimize lost experiment time and accelerate the understanding, interpretation, and planning of fusion experiments. IIP will allow to reap maximum benefits from the project's scientific and technological achievements, make the ITER results accessible to hundreds of researchers worldwide. This will facilitate collaboration, dramatically increasing the pace of scientific and technological discovery and the rate at which practical use is made of these discoveries.As the first of its kind, the ITER Information Plant could be used in the future as a prototype IT system for national and international fusion projects, in which multicountry collaboration, distributed work sites and operations are catalysts for success.

Putvinskaya, N.; Bulasheva, N.; Cole, G.; Dillon, T.; Frieman, E.; Sabado, M.; Schissel, D. (and others)

2005-04-15T23:59:59.000Z

158

IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, VOL. 14, NO. 2, JUNE 2004 1519 Tcs Tests and Performance Assessment of the ITER  

E-Print Network [OSTI]

racetrack coil is wound in double pancakes in the grooves of stainless steel radial plates using dual and Performance Assessment of the ITER Toroidal Field Model Coil (Phase II) R. Zanino, M. Bagnasco, G. Dittrich, W of Forschungszentrum Karlsruhe, Germany: in Phase I, completed in 2001, the coil was tested in its self-field, while

Hampshire, Damian

159

ITER vacuum vessel design (D201 subtask 1.3 and subtask 3). Final report  

SciTech Connect (OSTI)

ITER Task No. D201, Vacuum Vessel Design (Subtask 1.3 and Subtask 3), was initiated to propose and evaluate local vacuum vessel reinforcement alternatives in proximity to the Neutral Beam, Radial Mid-Plane, Top, and Divertor Ports. These areas were reported to be highly stressed regions based on the results of preliminary stress analyses performed by the USHT (US Home Team) and the ITER Joint Central Team (JCT) at the Garching JWS (Joint Work Site). Initial design activities focused on the divertor port region which was reported to experience the highest stress intensities. Existing stress analysis models and results were reviewed with the USHT stress analysts to obtain an overall understanding of the vessel response to the various applied loads. These reviews indicated that the reported stress intensities in the divertor port region were significantly affected by the loads applied to the vessel in adjacent regions.

NONE

1996-08-01T23:59:59.000Z

160

Iterative procedure for in-situ EUV optical testing with an incoherent source  

SciTech Connect (OSTI)

We propose an iterative method for in-situ optical testing under partially coherent illumination that relies on the rapid computation of aerial images. In this method a known pattern is imaged with the test optic at several planes through focus. A model is created that iterates through possible aberration maps until the through-focus series of aerial images matches the experimental result. The computation time of calculating the through-focus series is significantly reduced by a-SOCS, an adapted form of the Sum Of Coherent Systems (SOCS) decomposition. In this method, the Hopkins formulation is described by an operator S which maps the space of pupil aberrations to the space of aerial images. This operator is well approximated by a truncated sum of its spectral components.

Miyawaka, Ryan; Naulleau, Patrick; Zakhor, Avideh

2009-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Design of the ITER First Wall and Blanket A. Rene Raffray  

E-Print Network [OSTI]

Design of the ITER First Wall and Blanket A. Rene Raffray TKM, Internal Components Division ITER-mail: mario.merola@iter.org Abstract--This paper summarizes the status of the ITER blanket system design and describes some of the key R&D activities in support of the design with the goal of starting procurement

Raffray, A. René

162

Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials  

E-Print Network [OSTI]

Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials, Russian Federation Abstract Within the framework of the ITER Test Blanket Working Group, the ITER Parties have made several proposals for test blanket modules to be tested in ITER from the first day of H

Abdou, Mohamed

163

ITER: The International Thermonuclear Experimental Reactor and the Nuclear Weapons Proliferation  

E-Print Network [OSTI]

militarytechnical reasons and implications of the very probable siting of ITER (the International Thermonuclear

André Gsponer; Jean-pierre Hurni

2004-01-01T23:59:59.000Z

164

Inside ITER seminar on History of Fusion Page 1 History of Fusion  

E-Print Network [OSTI]

Union thermonuclear explosion 400kT #12;Inside ITER seminar on History of Fusion Page 4 Big IvanInside ITER seminar on History of Fusion Page 1 History of Fusion Personal view V. Chuyanov 9 July 2009 Special thanks to ITER Communication Division. #12;Inside ITER seminar on History of Fusion Page 2

165

Numerical simulations of welds of thick steel pieces of interest for the thermonuclear fusion ITER machine  

E-Print Network [OSTI]

Numerical simulations of welds of thick steel pieces of interest for the thermonuclear fusion ITER machine

Carmignani, B

2005-01-01T23:59:59.000Z

166

Dale M. Meade MFE Plenary Session on ITER Costs  

E-Print Network [OSTI]

FIRE Lighting the Way to Fusion http://fire.pppl.gov A Comparison of Unit Costs for FIRE and ITER #12;A Comparison of Unit Costs for FIRE and ITER · A simple rule of thumb for comparing costs of similar devices.14m) Weight FIREITERPCAS 0.25 $M/tonne 0.88 $M/tonne ARIES-RS (5.5m) First of a Kind #12;Comparison

167

Visible and Infrared Optical Design for the ITER Upper Ports  

SciTech Connect (OSTI)

This document contains the results of an optical design scoping study of visible-light and infrared optics for the ITER upper ports, performed by LLNL under contract for the US ITER Project Office. ITER is an international collaboration to build a large fusion energy tokamak with a goal of demonstrating net fusion power for pulses much longer than the energy confinement time. At the time of this report, six of the ITER upper ports are planned to each to contain a camera system for recording visible and infrared light, as well as other diagnostics. the performance specifications for the temporal and spatial resolution of this system are shown in the Section II, Functional Specifications. They acknowledge a debt to Y. Corre and co-authors of the CEA Cadarache report ''ITER wide-angle viewing and thermographic and visible system''. Several of the concepts used in this design are derived from that CEA report. The infrared spatial resolution for optics of this design is diffraction-limited by the size of the entrance aperture, at lower resolution than listed in the ITER diagnostic specifications. The size of the entrance aperture is a trade-off between spatial resolution, optics size in the port, and the location of relay optics. The signal-to-noise ratio allows operation at the specified time resolutions.

Lasnier, C; Seppala, L; Morris, K; Groth, M; Fenstermacher, M; Allen, S; Synakowski, E; Ortiz, J

2007-03-01T23:59:59.000Z

168

Iterative Solution of Elliptic Equations with a Small Parameter  

E-Print Network [OSTI]

and engineering are modelled by partial differ- ential equations involving a small parameter defining a certain are positive semi-definite linear partial differential operators, such that the operator t2 L1 +L0 is coercive the properties of the operators Li and the vectors x and b describe the unknown u and the load f with respect

Segatti, Antonio

169

Development of the Long Pulse Negative Ion Source for ITER  

SciTech Connect (OSTI)

A model of the ion source designed for the neutral beam injectors of the International Thermonuclear Experimental Reactor (ITER), the KAMABOKO III ion source, is being tested on the MANTIS test stand at the DRFC Cadarache in collaboration with JAERI, Japan, who designed and supplied the ion source. The ion source is attached to a 3 grid 30 keV accelerator (also supplied by JAERI) and the accelerated negative ion current is determined from the energy deposited on a calorimeter located 1.6 m from the source.During experiments on MANTIS three adverse effects of long pulse operation were found: The negative ion current to the calorimeter is {approx_equal}50% of that obtained from short pulse operation Increasing the plasma grid (PG) temperature results in {<=}40% enhancement in negative ion yield, substantially below that reported for short pulse operation, {>=}100%. The caesium 'consumption' is up to 1500 times that expected.Results presented here indicate that each of these is, at least partially, explained by thermal effects. Additionally presented are the results of a detailed characterisation of the source, which enable the most efficient mode of operation to be identified.

Hemsworth, R.S.; Svensson, L.; Esch, H.P.L. de; Krylov, A.; Massmann, P. [Association EURATOM-CEA, CEA/DSM/DRFC, CEA-Cadarache, 13108 St Paul-lez-Durance (France); Boilson, D. [Association EURATOM-DCU, PRL/NCPST, Glasnevin, Dublin 13 (Ireland); Fanz, U. [Association EURATOM-IPP, Max-Planck-Institut fuer Plasmaphysik D-85748 Garching (Germany); Zaniol, B. [CONSORZIO RFX Association EURATOM-ENEA, Corso Stati Uniti 4, I-35127 Padova (Italy)

2005-04-06T23:59:59.000Z

170

Second performance assessment iteration of the Greater Confinement Disposal facility at the Nevada Test Site  

SciTech Connect (OSTI)

The Greater Confinement Disposal (GCD) facility was established in Area 5 at the Nevada Test Site for containment of waste inappropriate for shallow land burial. Some transuranic (TRU) waste has been disposed of at the GCD facility, and compliance of this disposal system with EPA regulation 40 CFR 191 must be evaluated. We have adopted an iterative approach in which performance assessment results guide site data collection, which in turn influences the parameters and models used in performance assessment. The first iteration was based upon readily available data, and indicated that the GCD facility would likely comply with 40 CFR 191 and that the downward flux of water through the vadose zone (recharge) had a major influence on the results. Very large recharge rates, such as might occur under a cooler, wetter climate, could result in noncompliance. A project was initiated to study recharge in Area 5 by use of three environmental tracers. The recharge rate is so small that the nearest groundwater aquifer will not be contaminated in less than 10,000 years. Thus upward liquid diffusion of radionuclides remained as the sole release pathway. This second assessment iteration refined the upward pathway models and updated the parameter distributions based upon new site information. A new plant uptake model was introduced to the upward diffusion pathway; adsorption and erosion were also incorporated into the model. Several modifications were also made to the gas phase radon transport model. Plutonium solubility and sorption coefficient distributions were changed based upon new information, and on-site measurements were used to update the moisture content distributions. The results of the assessment using these models indicate that the GCD facility is likely to comply with all sections of 40 CFR 191 under undisturbed conditions.

Baer, T.A.; Emery, J.N. [GRAM, Inc., Albuquerque, NM (United States); Price, L.L. [Science Applications International Corp., Albuquerque, NM (United States); Olague, N.E. [Sandia National Labs., Albuquerque, NM (United States)

1994-04-01T23:59:59.000Z

171

Momentum space iterative solution of the time-dependent Schrödinger equation  

SciTech Connect (OSTI)

We present a novel approach, the iterative solution of the time-dependent Schrödinger equation (iTDSE model), for the investigation of atomic systems interacting with external laser fields. This model is the extension of the momentum-space strong-field approximation (MSSFA) [1], in which the Coulomb potential was considered only as a first order perturbation. In the iTDSE approach higher order terms were gradually introduced until convergence was achieved. Benchmark calculations were done on the hydrogen atom, and the obtained results were compared to the direct numerical solution [2].

Kiss, G. Zs.; Borbély, S.; Nagy, L. [Faculty of Physics, Babe?-Bolyai University, str. Kog?lniceanu nr. 1, 400084 Cluj (Romania)

2013-11-13T23:59:59.000Z

172

Recent progress on lower hybrid current drive and implications for ITER  

E-Print Network [OSTI]

The sustainment of steady-state plasmas in tokamaks requires efficient current drive systems. Lower Hybrid Current Drive (LHCD) is currently the most efficient method to generate a continuous additional off-axis toroidal plasma current as well as reduce the poloidal flux consumption during the plasma current ramp-up phase. The operation of the Tore Supra ITER-like LH launcher has demonstrated the capability to couple LH power at ITER-like power densities with very low reflected power during long pulses. In addition, the installation of eight 700kW/CW klystrons at the LH transmitter has allowed increasing the total LH power in long pulse scenarios. However, in order to achieve pure stationary LH sustained plasmas, some R\\&D are needed to increase the reliability of all the systems and codes, from the RF sources to the plasma scenario prediction. The CEA/IRFM is addressing some of these issues by leading a R\\&D program towards an ITER LH system and by the validation of an integrated LH modeling suite of...

Hillairet, Julien; Goniche, M; Achard, J; Armitano, A; Beckett, B; Belo, J; Berger-By, G; Corbel, E; Delpech, L; Decker, J; Dumont, R; Guilhem, D; Kazarian, F; Litaudon, X; Magne, R; Marfisi, L; Mollard, P; Namkung, W; Nilsson, E; Park, S; Peysson, Y; Preynas, M; Sharma, P K; Prou, M

2015-01-01T23:59:59.000Z

173

Negative Ion Based Heating and Diagnostic Neutral Beams for ITER  

SciTech Connect (OSTI)

To meet the requirements of the four operating and one start-up scenarios foreseen in the International Tokamak Experimental Reactor (ITER) a flexible heating mix will be required, which has to include a reliable contribution from neutral beams. The current baseline of ITER foresees 2 Heating Neutral Beam (HNB) systems based on negative ion technology, each operating at 1 MeV 40 A D{sup -} ions, and each capable of delivering up to 16.7 MW of D deg. to the ITER plasma. A 3rd HNB injector is foreseen as an upgrade option. In addition a dedicated Diagnostic Neutral Beam (DNB) injecting 100 keV 60 A of negative hydrogen ions will be available for charge exchange resonant spectroscopy (CXRS). The significant R and D effort necessary to meet the design requirements will be provided in the Neutral Beam Test Facility (NBTF), which is to be constructed in Padua, Italy. This paper gives an overview of the current status of the neutral beam (NB) systems and the chosen configuration. The ongoing integration effort into the ITER plant is highlighted and open interface issues are identified. It is shown how installation and maintenance logistics has influenced the design. ITER operating scenarios are briefly discussed, including start-up and commissioning. For example it is now envisaged to have a low current hydrogen phase of ITER operations, essentially for commissioning of the many auxiliary systems used on ITER. The low current limits the achievable plasma density, and hence the NB energy due to shine through limitations. Therefore a possible reconfiguration of the auxiliary heating systems is now being discussed. Other NB related issues identified by the ongoing design review process are emphasized and possible impact on the implementations of the HNB and DNB systems is indicated.

Schunke, B.; Bora, D.; Cordier, J.-J.; Hemsworth, R.; Tanga, A. [ITER Organization, Cadarache, 13108 St.-Paul-lez-Durance (France); Antoni, V. [Consorzio RFX, EURATOM-ENEA Association, Corso Stati Uniti 4, I-35127 (Italy); Bonicelli, T. [IPR, Bhat, Gandhinagar, Gujarat, 382428 (India); Chakraborty, A. [EFDA CSU, Boltzmannstrasse 2, D-85748, Garching (Germany); Inoue, T.; Watanabe, K. [JAEA, 801-1 Mukouyama, Naka-machi, Naka-gun, Ibaraki-ken 311-0193 (Japan)

2008-04-07T23:59:59.000Z

174

Power Handling in ITER: Divertor and Blanket Design and R&D M. Merola 1), D. Loesser 2), R. Raffray 1) on behalf of the ITER Organization, ITER  

E-Print Network [OSTI]

the thermonuclear plasma and cover an area of about 850 m2 . The main function of the divertor is minimizing the thermonuclear plasma. One of the most technically challenging components of the ITER machine are plasma-facing components (PFCs), which directly face the thermonuclear plasma and cover an area of about 850 m2

Raffray, A. René

175

ASI Student Involvement Outcomes ASI Student Involvement Outcomes  

E-Print Network [OSTI]

ASI Student Involvement Outcomes ASI Student Involvement Outcomes A student involved in the activities, programs, and services of the Associated Students, CSUF, Inc. develops and demonstrates achievement in the following (adopted from the University of Minnesota Student Success Outcomes

de Lijser, Peter

176

A Recommendation System for Preconditioned Iterative Solvers  

E-Print Network [OSTI]

. . . . . . . . . . . 162 c. Model Analysis . . . . . . . . . . . . . . . . . . . . 167 3. Performance Modeling . . . . . . . . . . . . . . . . . . . 168 a. Results on New Trials Over Train Matrices . . . . . . 169 b. Results on Unseen Test Matrices... . . . . . . . . . . . 169 c. Model Analysis . . . . . . . . . . . . . . . . . . . . 172 4. Top-k Recommendations . . . . . . . . . . . . . . . . . . 180 a. Results on New Trials Over Train Matrices . . . . . . 180 b. Results on Unseen Test Matrices . . . . . . . . . . . 188...

George, Thomas

2011-02-22T23:59:59.000Z

177

Description of the prototype diagnostic residual gas analyzer for ITER  

SciTech Connect (OSTI)

The diagnostic residual gas analyzer (DRGA) system to be used during ITER tokamak operation is being designed at Oak Ridge National Laboratory to measure fuel ratios (deuterium and tritium), fusion ash (helium), and impurities in the plasma. The eventual purpose of this instrument is for machine protection, basic control, and physics on ITER. Prototyping is ongoing to optimize the hardware setup and measurement capabilities. The DRGA prototype is comprised of a vacuum system and measurement technologies that will overlap to meet ITER measurement requirements. Three technologies included in this diagnostic are a quadrupole mass spectrometer, an ion trap mass spectrometer, and an optical penning gauge that are designed to document relative and absolute gas concentrations.

Younkin, T. R., E-mail: tyounkin@gatech.edu [Fusion and Materials for Nuclear Systems Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-6169 (United States); Georgia Institute of Technology, Woodruff School of Mechanical Engineering – Nuclear and Radiological Engineering Program, Atlanta, Georgia 30332 (United States); Biewer, T. M.; Klepper, C. C.; Marcus, C. [Fusion and Materials for Nuclear Systems Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-6169 (United States)

2014-11-15T23:59:59.000Z

178

Diamond neutral particle spectrometer for fusion reactor ITER  

SciTech Connect (OSTI)

A compact diamond neutral particle spectrometer with digital signal processing has been developed for fast charge-exchange atoms and neutrons measurements at ITER fusion reactor conditions. This spectrometer will play supplementary role for Neutral Particle Analyzer providing 10 ms time and 30 keV energy resolutions for fast particle spectra in non-tritium ITER phase. These data will also be implemented for independent studies of fast ions distribution function evolution in various plasma scenarios with the formation of a single fraction of high-energy ions. In tritium ITER phase the DNPS will measure 14 MeV neutrons spectra. The spectrometer with digital signal processing can operate at peak counting rates reaching a value of 10{sup 6} cps. Diamond neutral particle spectrometer is applicable to future fusion reactors due to its high radiation hardness, fast response and high energy resolution.

Krasilnikov, V.; Amosov, V.; Kaschuck, Yu.; Skopintsev, D. [Institution PROJECT CENTER ITER, 1, Akademik Kurchatov Sq., Moscow (Russian Federation)

2014-08-21T23:59:59.000Z

179

Iterative Estimation Maximization for Stochastic Linear Programs ...  

E-Print Network [OSTI]

We analyze the performance of IEM from a column generation point of view ...... To generate the whole frontier, we add the following constraint to Model (M4).

2009-03-26T23:59:59.000Z

180

Iterative methods for solving nonlinear problems of nuclear reactor criticality  

SciTech Connect (OSTI)

The paper presents iterative methods for calculating the neutron flux distribution in nonlinear problems of nuclear reactor criticality. Algorithms for solving equations for variations in the neutron flux are considered. Convergence of the iterative processes is studied for two nonlinear problems in which macroscopic interaction cross sections are functionals of the spatial neutron distribution. In the first problem, the neutron flux distribution depends on the water coolant density, and in the second one, it depends on the fuel temperature. Simple relationships connecting the vapor content and the temperature with the neutron flux are used.

Kuz'min, A. M., E-mail: mephi.kam@mail.ru [National Research Nuclear University MEPhI (Russian Federation)

2012-12-15T23:59:59.000Z

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Iterative reconstruction of the detector response for medical gamma cameras  

E-Print Network [OSTI]

Statistical event reconstruction techniques can give better results for gamma cameras than the traditional centroid method. However, implementation of such techniques requires detailed knowledge of the PMT light response functions. Here we describe an iterative technique which allows to obtain the response functions from flood irradiation data without imposing strict requirements on the spatial uniformity of the event distribution. A successful application of the technique for medical gamma cameras is demonstrated using both simulated and experimental data. We show that this technique can be used for monitoring of the photomultiplier gain variations. An implementation of the iterative reconstruction technique capable of operating in real-time is also presented.

Morozov, A; Alves, F; Domingos, V; Martins, R; Neves, F; Chepel, V

2015-01-01T23:59:59.000Z

182

Bragg x-ray survey spectrometer for ITER  

SciTech Connect (OSTI)

Several potential impurity ions in the ITER plasmas will lead to loss of confined energy through line and continuum emission. For real time monitoring of impurities, a seven channel Bragg x-ray spectrometer (XRCS survey) is considered. This paper presents design and analysis of the spectrometer, including x-ray tracing by the Shadow-XOP code, sensitivity calculations for reference H-mode plasma and neutronics assessment. The XRCS survey performance analysis shows that the ITER measurement requirements of impurity monitoring in 10 ms integration time at the minimum levels for low-Z to high-Z impurity ions can largely be met.

Varshney, S. K.; Jakhar, S. [ITER-India, Institute for Plasma Research, Bhat, Gandhinagar, Gujarat 382428 (India); Barnsley, R. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); O'Mullane, M. G. [Department of Physics, University of Strathclyde, Glasgow G4 0NG (United Kingdom)

2012-10-15T23:59:59.000Z

183

Helium-cooled lithiuim compound suspension blanket concept for ITER  

SciTech Connect (OSTI)

This blanket concept uses a dilute suspension of fine solid breeder particles (Li/sub 2/O, LiAlO/sub 2/, or Li/sub 4/SiO/sub 4/) in a carrier gas (He) as the coolant and the tritium breeding stream. A small fraction of this stream is processed outside the reactor for tritium recovery. The blanket consists of a beryllium multiplier and carbon/steel reflector. A steel clad is used for all materials. A carbon reflector is employed to reduce the beryllium thickness used in the blanket for a specific tritium breeding ratio. The breeder particle size has to exceed few microns (greater than or equal to2 microns) to avoid sticking problems on the cold surfaces of the heat exchanger. The helium gas pressure is in the range of 2 to 3 MPa to carry the blanket and the heat exchanger loop. The solid breeder concentration in the helium stream is 1 to 5 volume percent. A high lithium-6 enrichment is used to produce a high tritium breeding ratio and to reduce the breeder concentration in the helium gas. At a lithium-6 enrichment of 90%, the local tritium breeding ratio is 2.03 based on a one-dimensional poloidal model. The total thickness of the helium stream is only 4 cm out of the 50 cm total blanket thickness. The blanket uses a 35 cm of beryllium for neutron multiplication. A simple multi-layer design is employed where the blanket sector has the helium coolant flowing in the poloidal direction. The blanket concept has several unique advantages which are very beneficial for fusion reactors including ITER. 10 refs., 2 tabs.

Gohar, Y.; Baker, C.C.; Attaya, H.; Billone, M.; Clemmer, R.C.; Finn, P.A.; Hassanein, A.; Johnson, C.E.; Majumdar, S.; Mattas, R.F.

1988-08-01T23:59:59.000Z

184

A PRELIMINARY ASSESSMENT OF THE OCCUPATIONAL RADIATION EXPOSURE FROM MAINTAINING THE US ITER DCLL TBM  

SciTech Connect (OSTI)

This paper details an Occupational Radiation Exposure (ORE) analysis performed for the US International Thermonuclear Experimental Reactor (ITER) Dual Coolant Lead Lithium (DCLL) Test Blanket Module (TBM). This ORE analysis was performed with the QADMOD dose code for maintenance activities anticipated for the US DCLL TBM concept and its ancillary systems. Identification of the maintenance tasks that will have to be performed and estimates of the time required to perform these tasks were developed based on either expert opinion or on industrial maintenance experience for similar technologies. This paper details the modeling activity and the calculated doses for the maintenance activities envisioned for the US DCLL TBM.

B. J. Merrill; L. C. Cadwallader; M. Dagher

2008-09-01T23:59:59.000Z

185

Fusion Materials Science and Technology Research Needs: Now and During the ITER era  

SciTech Connect (OSTI)

The plasma facing components, first wall and blanket systems of future tokamak-based fusion power plants arguably represent the single greatest materials engineering challenge of all time. Indeed, the United States National Academy of Engineering has recently ranked the quest for fusion as one of the top grand challenges for engineering in the 21st Century. These challenges are even more pronounced by the lack of experimental testing facilities that replicate the extreme operating environment involving simultaneous high heat and particle fluxes, large time varying stresses, corrosive chemical environments, and large fluxes of 14-MeV peaked fusion neutrons. This paper will review, and attempt to prioritize, the materials research and development challenges facing fusion nuclear science and technology into the ITER era and beyond to DEMO. In particular, the presentation will highlight the materials degradation mechanisms we anticipate to occur in the fusion environment, the temperature- displacement goals for fusion materials and plasma facing components and the near and long-term materials challenges required for both ITER, a fusion nuclear science facility and longer term ultimately DEMO.

Wirth, Brian D.; Kurtz, Richard J.; Snead, Lance L.

2013-09-30T23:59:59.000Z

186

Brussels advocates a lone rider for ITER 09/22/2004 Edition  

E-Print Network [OSTI]

can advance alone to establish the thermonuclear reactor experimental ITER in Cadarache. France in the construction of the future experimental thermonuclear reactor ITER, if Brussels does not manage to convince

187

Perspectives on US program support of FNSF and ITER in coming decade  

E-Print Network [OSTI]

-pulse PMI, stellarator) · U.S. Burning Plasma Organization could also expand beyond ITER to incorporate FNSP facility support a staged approach? (PMI FNSF CTF Pilot?) · Which ITER physics and technology can

188

Brussels, 13 May 2003 Europe moves into position to host ITER  

E-Print Network [OSTI]

by the EU on the agreement on the construction, operation and decommissioning of ITER. For further://www.iter.org/ #12;3 ANNEX What is energy from nuclear fusion? Research in the field of fusion has been going

189

A Transport Synthetic Acceleration method for transport iterations  

E-Print Network [OSTI]

that discretization enhances TSA performance. We then propose to implement a Conjugate Gradient method on the low-order problem, to use a crude quadrature set in the low-order problem and to set the number of low-order iterations per transport sweep to a finite value...

Ramone, Gilles Lionel

1996-01-01T23:59:59.000Z

190

Sabina Griffith Email: Sabina.Griffith@iter.org  

E-Print Network [OSTI]

Energy Agency (IAEA). In recognition of his life-long contribution to ITER, a moment of silence was approved at the extraordinary IC on July 28, 2010. This report included a new strategy for cost savings with representatives of the local communities, were invited to celebrate the official start of construction

191

Overview of Recent Developments in Pellet Injection for ITER  

SciTech Connect (OSTI)

Pellet injection is the primary fueling technique planned for core fueling of ITER burning plasmas. Also, the injection of relatively small pellets to purposely trigger rapid small edge localized modes (ELMs) has been proposed as a possible solution to the heat flux damage from larger natural ELMs likely to be an issue on the ITER divertor surfaces. The ITER pellet injection system is designed to inject pellets into the plasma through both inner and outer wall guide tubes. The inner wall guide tubes will provide high throughput pellet fueling while the outerwall guide tubes will be used primarily to trigger ELMs at a high frequency (>15 Hz). The pellet fueling rate ofeach injector is to be up to 120 Pa-m3/s, which will require the formation of solid D-T at a volumetric rate of ~1500 mm3/s. Two injectors are to be provided for ITER at the startup with a provision for up to six injectorsduring the D-T phase. The required throughput of each injector is greater than that of any injector built to date, and a novel twin-screw continuous extrusion system is being developed to meet the challenging design parameters. Status of the development activities will be presented, highlighting recent progress.

Combs, Stephen Kirk [ORNL; Baylor, Larry R [ORNL; Meitner, Steven J [ORNL; Caughman, John B [ORNL; Rasmussen, David A [ORNL; Maruyama, So [ITER Organization, Cadarache, France

2012-01-01T23:59:59.000Z

192

Industrial opportunities on the International Thermonuclear Experimental Reactor (ITER) project  

SciTech Connect (OSTI)

Industry has been a long-term contributor to the magnetic fusion program, playing a variety of important roles over the years. Manufacturing firms, engineering-construction companies, and the electric utility industry should all be regarded as legitimate stakeholders in the fusion energy program. In a program focused primarily on energy production, industry`s future roles should follow in a natural way, leading to the commercialization of the technology. In a program focused primarily on science and technology, industry`s roles, in the near term, should be, in addition to operating existing research facilities, largely devoted to providing industrial support to the International Thermonuclear Experimental Reactor (ITER) Project. Industrial opportunities on the ITER Project will be guided by the amount of funding available to magnetic fusion generally, since ITER is funded as a component of that program. The ITER Project can conveniently be discussed in terms of its phases, namely, the present Engineering Design Activities (EDA) phase, and the future (as yet not approved) construction phase. 2 refs., 3 tabs.

Ellis, W.R. [Raytheon Engineers and Constructors, New York, NY (United States)

1996-12-01T23:59:59.000Z

193

Plans for U.S. Contributions to ITER  

E-Print Network [OSTI]

· Project Management/Support · International Team Support · Magnets, Cooling Water, Blanket Shielding transmission lines 15% of port-based diagnostics 7 Central Solenoid windings 75% Cooling for divertor, vacuum components 8% of Toroidal Field conductor Steady-state power supplies #12;US ITER In-kind Hardware

194

Iterative Detection and Channel Estimation for Thomas Zemen  

E-Print Network [OSTI]

Iterative Detection and Channel Estimation for MC­CDMA Thomas Zemen Siemens Austria, PSE PRO RCD ErdbergerlË?ande 26 A­1031 Vienna, Austria E­mail: thomas.zemen@siemens.com Joachim Wehinger, Christoph wireless communication systems. Their equalization is based on the fast Fourier transform, allowing

Müller, Ralf R.

195

Iterative Detection and Channel Estimation for Thomas Zemen  

E-Print Network [OSTI]

Iterative Detection and Channel Estimation for MC-CDMA Thomas Zemen Siemens Austria, PSE PRO RCD Erdbergerl¨ande 26 A-1031 Vienna, Austria E-mail: thomas.zemen@siemens.com Joachim Wehinger, Christoph communication systems. Their equalization is based on the fast Fourier transform, allowing for an efficient

Zemen, Thomas

196

Enantioselective Total Synthesis of (-)-Pironetin: Iterative Aldol Reactions  

E-Print Network [OSTI]

titanium mediated iterative aldol reactions. Key steps in this synthesis include an acetal aldol reaction to establish the stereochemistry at C8 and C9, an acetate aldol reaction, and "Evans" syn aldol reaction and allylation methods,4m Enders and co-workers have disclosed a convergent total synthesis relying on RAMP

197

About the Limiting Behaviour of Iterated Robust Morphological Operators  

E-Print Network [OSTI]

Guanajuato, Gto., Mexico horebeek@cimat.mx 2 Freie Universitat Berlin, Institut fur Informatik Tacostr. 9 of morphological operators. To this purpose, we describe the implied iterative process by a discrete dynamical morphology is an important branch of non-linear signal process- ing. It has its roots in discrete geometry

Van Horebeek, Johan

198

ACCELERATED SPATIO-TEMPORAL WAVELET TRANSFORMS: AN ITERATIVE TRAJECTORY ESTIMATION. *  

E-Print Network [OSTI]

ACCELERATED SPATIO-TEMPORAL WAVELET TRANSFORMS: AN ITERATIVE TRAJECTORY ESTIMATION. * Jean accelerated motion in spatio-temporal discrete sig- nals. It is assumed that the digital signals of inter- est, they contain all the orders of acceleration. The purpose of this work is to estimate the trajectory

Wickerhauser, M. Victor

199

ACCELERATING REGULARIZED ITERATIVE CT RECONSTRUCTION ON COMMODITY GRAPHICS HARDWARE (GPU)  

E-Print Network [OSTI]

overhead to very moderate levels. Index Terms-- Iterative Reconstruction, Computed Tomography, Ordered Klaus Mueller Center for Visual Computing, Computer Science Department, Stony Brook University ABSTRACT) is the overall theme in many efforts to lower these exposures. Effective methods here include limiting either

Mueller, Klaus

200

Iteration Bounds for Finding the ?-Stationary Points for Structured ...  

E-Print Network [OSTI]

Oct 15, 2014 ... where ? = p/q with 1/p + 1/q = 1, then we prove that the new algorithms have an overall iteration complexity bound of O(1/?q) in finding an ?-stationary ...... + Mr,. (35) which means that if the perturbation is small, then the ...

2014-10-15T23:59:59.000Z

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Analysis of Disruption Scenarios Their Possible Mitigation in ITER  

E-Print Network [OSTI]

of the design) - Database analysis and physics guidelines for current quench rate and halo current - Simulation [MA/m2 ] Te=2eV Te=5eV Te=8eV ITER 9 MA 24 MA =0.72 m-3 #12;· Good measure for quench time

202

Joint News Release CHINA AND THE U.S. JOIN ITER NEGOTIATIONS  

E-Print Network [OSTI]

to the importance of ITER both in the Summit meeting with President Putin and in his speech at the Kurchatov

203

The Role of the Inner Product in Stopping Criteria for Conjugate Gradient Iterations  

E-Print Network [OSTI]

stopping criteria are derived for conjugate gradient (CG) methods, based on iteration parameters criteria, conjugate gradient methods, B-normal matrices 1 Introduction Unlike a direct method, an iterative1 The Role of the Inner Product in Stopping Criteria for Conjugate Gradient Iterations S. F. Ashby

Holst, Michael J.

204

Linear iterative refinement method for the rapid simulation of borehole nuclear measurements: Part I --Vertical wells  

E-Print Network [OSTI]

Linear iterative refinement method for the rapid simulation of borehole nuclear measurements: Part a new linear iterative refinement method to simulate nuclear borehole measurements accurately included in the in- tegral form of Boltzmann's equation. The linear iterative refine- ment method accounts

Torres-Verdín, Carlos

205

ANALYSES AND PRELIMINARY RESULTS OF AN UPDATED ITER RADIOACTIVE WASTE ASSESSMENT  

E-Print Network [OSTI]

ANALYSES AND PRELIMINARY RESULTS OF AN UPDATED ITER RADIOACTIVE WASTE ASSESSMENT S. ZHENG,a * R aimed at updating the ITER radioactive inventory assessment and assisting the waste manage- ment operations, and waste management processes and services. KEYWORDS: ITER, radioactive waste management

206

36.th EPS-CPP, June 30.th 2009 -Sofia ITER Session  

E-Print Network [OSTI]

36.th EPS-CPP, June 30.th 2009 - Sofia ITER Session F. Zonca - The FAST Proposal Associazione Tor Vergata Univ. of Catania #12;36.th EPS-CPP, June 30.th 2009 - Sofia ITER Session F. Zonca & construction #12;36.th EPS-CPP, June 30.th 2009 - Sofia ITER Session F. Zonca - The FAST Proposal Associazione

Zonca, Fulvio

207

TRITIUM ANALYSIS OF A WATER-COOLED SOLID BREEDER BLANKET FOR ITER*  

E-Print Network [OSTI]

TRITIUM ANALYSIS OF A WATER-COOLED SOLID BREEDER BLANKET FOR ITER* G. Federici, A.R. Raffray, M breeder blanket for the InternationalThermonuclearExperimental Reac- tor (ITER) obtained from the tritium-cooled solid breeder blanket has been proposed for the ITER tritium-producing blanket [2]. The breeder is oper

Abdou, Mohamed

208

Innovation is Key from ITER to DEMO M. Porkolab, L. Bromberg, M. Greenwald, A. Hubbard,  

E-Print Network [OSTI]

PMI in tokamak · SS current drive & heating · Divertor solution compatible with core Porkolab_FPA_2013 #12;For PMI, the step from ITER to DEMO will be enormous. ITER ARIES- ACT1 ARIES- ACT2 R(m) 6.2 6.25 9/R than ITER Factor of 105 increase in pulse length Innovative solutions to critical PMI challenges

209

FPA 30 year Anniversary Meeting, Washington, 2 December 2009 Slide 1 Status of ITER  

E-Print Network [OSTI]

FPA 30 year Anniversary Meeting, Washington, 2 December 2009 Slide 1 Status of ITER Fusion Power, 2 December 2009 Slide 2 Machine mass: 23350 t (cryostat + VV + magnets) - shielding, divertor Anniversary Meeting, Washington, 2 December 2009 Slide 3 TheThe Final ITER SiteFinal ITER Site Tokamak Hall

210

Annual Report of the EURATOM/CCFE Fusion Programme 2011/12 8 ITER Systems  

E-Print Network [OSTI]

and undertake leading or major roles in the design and R&D of ITER specialist systems (Heating, Diagnostics and Remote Handling etc.) in Europe; 8ITERSystems · Seek to play other design roles in R&D of ITER specialist its substantial role in the following key ITER systems: · Ion Cyclotron Resonance Heating (ICRH

211

ITER & Fusion Research Reference: MEMO/10/165 Date: 05/05/2010  

E-Print Network [OSTI]

ITER & Fusion Research Reference: MEMO/10/165 Date: 05/05/2010 HTML: EN PDF: EN DOC: EN MEMO/10/165 Brussels, 5th May 2010 ITER & Fusion Research The Commission has adopted a Communication to the European for International Thermonuclear Experimental Reactor (ITER), which have more than doubled the costs for Europe (to

212

A turbulent transport network model in MULTIFLUX coupled with TOUGH2  

SciTech Connect (OSTI)

A new numerical method is described for the fully iterated, conjugate solution of two discrete submodels, involving (a) a transport network model for heat, moisture, and airflows in a high-permeability, air-filled cavity; and (b) a variably saturated fractured porous medium. The transport network submodel is an integrated-parameter, computational fluid dynamics solver, describing the thermal-hydrologic transport processes in the flow channel system of the cavity with laminar or turbulent flow and convective heat and mass transport, using MULTIFLUX. The porous medium submodel, using TOUGH2, is a solver for the heat and mass transport in the fractured rock mass. The new model solution extends the application fields of TOUGH2 by integrating it with turbulent flow and transport in a discrete flow network system. We present demonstrational results for a nuclear waste repository application at Yucca Mountain with the most realistic model assumptions and input parameters including the geometrical layout of the nuclear spent fuel and waste with variable heat load for the individual containers. The MULTIFLUX and TOUGH2 model elements are fully iterated, applying a programmed reprocessing of the Numerical Transport Code Functionalization model-element in an automated Outside Balance Iteration loop. The natural, convective airflow field and the heat and mass transport in a representative emplacement drift during postclosure are explicitly solved in the new model. The results demonstrate that the direction and magnitude of the air circulation patterns and all transport modes are strongly affected by the heat and moisture transport processes in the surrounding rock, justifying the need for a coupled, fully iterated model solution such as the one presented in the paper.

Danko, G.; Bahrami, D.; Birkholzer, J.T.

2011-02-15T23:59:59.000Z

213

active user involvement: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

architecture. DBS was implemented on the Nano-Threads Programming Model (NPM) as part of NANOS, a large-scale project involving the development of a runtime...

214

An iterative technique for the factorization of polynomials  

E-Print Network [OSTI]

FACTOR NUMBER 1 A(I, J) COEFFICIENTS OF F(X) 0. 09999999E 01 0. 40000000E 01 0. 0. 0. 20000000E 01 0. 80000000E 01 0. 9 00000 0. OE 01 0. 36000000E 02 0. 0. 0. 18000000E 02 0. 72000000E 02 ITER P(I, J) FOR THIS SET Of ITERATIONS 0. 09999999...E 0. 09999999E 0. 09999999E 0. 73 02 2 808E 0. 09999999E 0. 14229858E 0. 09999999E 0. 11079702E 0. 09999999E 0. 14843886E 0, 09999999E 0. 17027360E 0. 09999999E 0. 188503 02E 0. 09999999E 01 01 01 00 01 01 01 01 01 01 01 01...

Gray, Jerry Edwin

2012-06-07T23:59:59.000Z

215

Water-cooled solid-breeder blanket concept for ITER  

SciTech Connect (OSTI)

A water cooled solid-breeder blanket concept was developed for ITER. The main function of this blanket is to produce the necessary tritium for the ITER operation. Several design features are incorporated in this blanket concept to increase its attractiveness. The main features are the following: (a) a multilayer concept which reduces fabrication cost; (b) a simple blanket configuration which results in reliability advantages; (c) a very small breeder volume is employed to reduce the tritium inventory and the blanket cost; (d) a high tritium breeding ratio eliminates the need for an outside tritium supply; (e) a low-pressure system decreases the required steel fraction for structural purposes; (f) a low-temperature operation reduces the swelling concerns for beryllium; and (g) the small fractions of structure and breeder materials used in the blanket reduce the decay heat source. The key features and design analyses of this blanket are summarized in this paper.

Gohar, Y.; Baker, C.C.; Attaya, H.; Billone, M.; Clemmer, R.C.; Finn, P.A.; Hassanein, A.; Johnson, C.E.; Majumdar, S.; Mattas, R.F.

1989-03-01T23:59:59.000Z

216

U. S. ITER shield and blanket design activities  

SciTech Connect (OSTI)

This paper summarizes nuclear-related work in support of the U.S. effort for the Internatinoal Thermonuclear Experimental Reactor (ITER) Study. Primary tasks carried out during the past year include design improvements of the inboard shield developed for the TIBER concept, scoping studies of a variety of tritium breeding blanket options, development of necessary design guidelines and evaluation criteria for the blanket options, further safety considerations related to nuclear components, and issues regarding structural materials for an ITER device. The blanket concepts considered are the aqueous/Li salt solution, a water-cooled, solid-breeder blanket, a helium-cooled, solid-breeder blanket, a helium-cooled, solid-breeder blanket, a blanket cooled by helium containing lithium-bearing particulates, and a blanket concept based on breeding tritium from He/sup 3/.

Baker, C.C.

1989-03-01T23:59:59.000Z

217

Krylov subspace iteration for eigenvalue response matrix calculations  

SciTech Connect (OSTI)

Recent work has revisited the eigenvalue response matrix method as an approach for reactor core analyses. In its most straightforward form, the method consists of a two-level Eigen problem. An outer Picard iteration updates the k-eigenvalue, while the inner Eigen problem imposes current continuity between coarse meshes. In this paper, several Eigen solvers are evaluated for this inner problem, using several 2-D diffusion benchmarks as test cases. The results indicate both the explicitly-restarted Arnoldi and the Krylov-Schur methods are up to an order of magnitude more efficient than power iteration. This increased efficiency makes the nested eigenvalue formulation more effective than the ILU-preconditioned Newton-Krylov formulation previously studied. (authors)

Roberts, J. A.; Forget, B. [Massachusetts Inst. of Technology, 77 Massachusetts Ave., Cambridge, MA 02141 (United States)

2012-07-01T23:59:59.000Z

218

Engineering and manufacturing of ITER first mirror mock-ups  

SciTech Connect (OSTI)

Most of the ITER optical diagnostics aiming at viewing and monitoring plasma facing components will use in-vessel metallic mirrors. These mirrors will be exposed to a severe plasma environment and lead to an important tradeoff on their design and manufacturing. As a consequence, investigations are carried out on diagnostic mirrors toward the development of optimal and reliable solutions. The goals are to assess the manufacturing feasibility of the mirror coatings, evaluate the manufacturing capability and associated performances for the mirrors cooling and polishing, and finally determine the costs and delivery time of the first prototypes with a diameter of 200 and 500 mm. Three kinds of ITER candidate mock-ups are being designed and manufactured: rhodium films on stainless steel substrate, molybdenum on TZM substrate, and silver films on stainless steel substrate. The status of the project is presented in this paper.

Joanny, M.; Travere, J. M.; Salasca, S.; Corre, Y. [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France); Marot, L. [Department of Physics, University of Basel, Klingelbergstrasse 82, CH-4056 Basel (Switzerland); Thellier, C.; Gallay, G.; Cammarata, C.; Passier, B.; Ferme, J. J. [SESO, 305 Rue Louis Armand CS 30504, 13593 Aix-en-Provence Cedex 3 (France)

2010-10-15T23:59:59.000Z

219

An Overview of US ITER Test Blanket Module Program  

SciTech Connect (OSTI)

A testing strategy and corresponding test plan have been presented for the two proposed US candidate breeder blankets: 1) a helium-cooled solid breeder concept with ferritic steel structure and Be neutron multiplier, but without a fully independent TBM, and 2) a dual-coolant helium-cooled ferritic steel structure with self-cooled LiPb breeding zone that uses a flow channel insert as MHD and thermal insulator. Example test module designs, and configuration choices for each line of ITER TBM are shown and discussed in the paper. In addition, near-term R&D items for decision-making on testing of both solid breeder and dual-coolant PbLi liquid breeder blanket concepts in ITER are identified.

Ying, A.; Abdou, Mohamed A.; Wong, Clement; Malang, S.; Morley, Neil B.; Sawan, M.; Merrill, Brad; Sze, Dai Kai; Kurtz, Richard J.; Willms, Scott; Ulrickson, Mike; Zinkle, Steven J.

2006-01-01T23:59:59.000Z

220

Atomic Physics in the Quest for Fusion Energy and ITER  

SciTech Connect (OSTI)

The urgent quest for new energy sources has led developed countries, representing over half of the world population, to collaborate on demonstrating the scientific and technological feasibility of magnetic fusion through the construction and operation of ITER. Data on high-Z ions will be important in this quest. Tungsten plasma facing components have the necessary low erosion rates and low tritium retention but the high radiative efficiency of tungsten ions leads to stringent restrictions on the concentration of tungsten ions in the burning plasma. The influx of tungsten to the burning plasma will need to be diagnosed, understood and stringently controlled. Expanded knowledge of the atomic physics of neutral and ionized tungsten will be important to monitor impurity influxes and derive tungsten concentrations. Also, inert gases such as argon and xenon will be used to dissipate the heat flux flowing to the divertor. This article will summarize the spectroscopic diagnostics planned for ITER and outline areas where additional data is needed.

Charles H. Skinner

2008-02-27T23:59:59.000Z

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
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221

Iterative solution of ordinary differential equations with polynomial coefficients  

E-Print Network [OSTI]

ITERATIVE SOLUTION OF ORDINARY DIFFERENTIAL EQUATIONS WITH POLYNOMIAL COEFFICIENTS A Thesis By JIMMIE CHARLES RHEA FOREHAND Submitted to the Graduate College of the Texas A&M University in partial fulfillment of the requirements... for the degree of MASTER OF SCIENCE August 1965 Major Subject Mathematics FAMILIES OF FIFTH ORDER RUNGE-KUTTA FORMULAS A Thesis By HARRY PAUL KONEN 4 0 0 IXI v 0 Approved as to style and content by: (Chairman of Committee) (Head of Departmen...

Forehand, Jimmie Charles Rhea

1965-01-01T23:59:59.000Z

222

Qualification of the Joints for the ITER Central Solenoid  

SciTech Connect (OSTI)

The ITER Central Solenoid has 36 interpancake joints, 12 bus joints, and 12 feeder joints in the magnet. The joints are required to have resistance below 4 nOhm at 45 kA at 4.5 K. The US ITER Project Office developed two different types of interpancake joints with some variations in details in order to find a better design, qualify the joints, and establish a fabrication process. We built and tested four samples of the sintered joints and two samples with butt-bonded joints (a total of eight joints). Both designs met the specifications. Results of the joint development, test results, and selection of the baseline design are presented and discussed in the paper. The ITER Central Solenoid (CS) consists of six modules. Each module is composed of six wound hexapancakes and one quadrapancake. The multipancakes are connected electrically and hydraulically by in-line interpancake joints. The joints are located at the outside diameter (OD) of the module. Cable in conduit conductor (CICC) high-current joints are critical elements in the CICC magnets. In addition to low resistivity, the CS joints must fit a space envelope equivalent to the regular conductor cross section and must have low hydraulic impedance and enough structural strength to withstand the hoop and compressive forces during operation, including cycling. This paper is the continuation of the work reported on the intermodule joints.

Martovetsky, N; Berryhill, A; Kenney, S

2011-09-01T23:59:59.000Z

223

Improved criticality convergence via a modified Monte Carlo iteration method  

SciTech Connect (OSTI)

Nuclear criticality calculations with Monte Carlo codes are normally done using a power iteration method to obtain the dominant eigenfunction and eigenvalue. In the last few years it has been shown that the power iteration method can be modified to obtain the first two eigenfunctions. This modified power iteration method directly subtracts out the second eigenfunction and thus only powers out the third and higher eigenfunctions. The result is a convergence rate to the dominant eigenfunction being |k{sub 3}|/k{sub 1} instead of |k{sub 2}|/k{sub 1}. One difficulty is that the second eigenfunction contains particles of both positive and negative weights that must sum somehow to maintain the second eigenfunction. Summing negative and positive weights can be done using point detector mechanics, but this sometimes can be quite slow. We show that an approximate cancellation scheme is sufficient to accelerate the convergence to the dominant eigenfunction. A second difficulty is that for some problems the Monte Carlo implementation of the modified power method has some stability problems. We also show that a simple method deals with this in an effective, but ad hoc manner.

Booth, Thomas E [Los Alamos National Laboratory; Gubernatis, James E [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

224

Water-cooled solid-breeder concept for ITER  

SciTech Connect (OSTI)

A water-cooled solid-breeder blanket concept was developed for ITER. The main function of this blanket is to produce the necessary tritium for the ITER operation. Several design features are incorporated in this blanket concept to increase its attractiveness. It is assumed that the blanket operation at commercial power reactor conditions can be sacrificed to achieve a high tritium breeding ratio with minimum additional research and development, and minimal impact on reactor design and operation. Operating temperature limits are enforced for each material to insure a satisfactory blanket performance. In fact, the design was iterated to maximize the tritium breeding ratio and satisfy these temperature limits. The other design constraint is to permit a large increase in the neutron wall loading without exceeding the temperature limits for the different blanket materials. The blanket concept contains 1.8 cm of Li/sub 2/O and 22.5 cm of beryllium both with a 0.8 density factor. The water coolant is isolated from the breeder material by several zones which reduces the tritium buildup in the water by permeation, reduces the chance for water-breeder interaction, and permits the breeder to operate at high temperature with a low temperature coolant. This improves the safety and environmental aspects of the blanket and eliminates the costly process of the tritium recovery from the water. The key features and design analysis of this blanket are summarized in this paper. 11 refs., 2 figs., 3 tabs.

Gohar, Y.; Baker, C.C.; Attaya, H.; Billone, M.; Clemmer, R.C.; Finn, P.A.; Hassanein, A.; Johnson, C.E.; Majumdar, S.; Mattas, R.F.

1988-08-01T23:59:59.000Z

225

Progress and present status of ITER cryoline system  

SciTech Connect (OSTI)

The cryoline system at ITER forms a very complex network localized inside the Tokamak building, on a dedicated plant bridge and in cryoplant areas. The cooling power produced in the cryoplant is distributed via these lines with a total length of about 3.7 km and interconnecting all the cold boxes of the cryogenic system as well as the cold boxes of various clients (magnets, cryopumps and thermal shield). Distinct layouts and polygonal geometry, nuclear safety and confinement requirements, difficult installation and in-service inspection/repair demand very high reliability and availability for the cryolines. The finalization of the building-embedded plates for supporting the lines, before the detailed design, has made this project technologically more challenging. The conceptual design phase has been completed and procurement arrangements have been signed with India, responsible for providing the system of cryolines and warm lines to ITER, as in kind contribution. The prototype test for the design and performance validation has been planned on a representative cryoline section. After describing the basic features and general layout of the ITER cryolines, the paper presents key design requirements, conceptual design approach, progress and status of the cryolines project as well as challenges to build such a complex cryoline system.

Badgujar, S.; Bonneton, M.; Chalifour, M.; Forgeas, A.; Serio, L. [ITER Organization, Route de Vinon sur Verdon, 13115 St. Paul lez Durance (France); Sarkar, B.; Shah, N. [ITER-India, Institute for Plasma Research, Bhat, Gandhinagar 382428 (India)

2014-01-29T23:59:59.000Z

226

Breeding channel for the ITER blanket with lithium-lead eutectic Li17Pb83  

SciTech Connect (OSTI)

The report contains some features of using Li{sub 17}Pb{sub 83} eutectic as breeder for ITER fusion reactor. The use of eutectic in the ITER blanket as breeding material has its own advantages. Results of improvements of lithium-lead blanket channels are described in the report. Design analysis, operation conditions of breeding channels, technique of filling up with eutectic and tritium recovery problems are considered. The eutectic detritization is performed outside and also inside the reactor without removing the eutectic from the blanket. The report contains a survey of investigations of eutectic and channel structure thermal-mechanical behavior, that was the cause of the up to date channel design improvement. The first stage of the thermal and mechanical tests results in change of the channel structure to the sectioning one. The comprehensive tests of the channel models including thermo-mechanical effect of eutectic on the channel structure at the different operating conditions of the channel including the accident ones, the techniques for handling with eutectic etc. to justify the design decisions concerning the breeding eutectic blanket. Suggestions for the further development of the channel design are presented.

Danilov, I.; Sidorov, A.; Strebkov, Y. [ENTEK-RDIPE, Moscow (Russian Federation)] [and others

1994-12-31T23:59:59.000Z

227

The neutral beam system for ITER is composed of two Heating and Current Drive (H&CD) injectors and  

E-Print Network [OSTI]

incorporated into ITER's Product Lifecycle Management (PLM) system Figure 3: Illustration of design progress

228

Iterative linear solvers in a 2D radiation-hydrodynamics code: Methods and performance  

SciTech Connect (OSTI)

Computer codes containing both hydrodynamics and radiation play a central role in simulating both astrophysical and inertial confinement fusion (ICF) phenomena. A crucial aspect of these codes is that they require an implicit solution of the radiation diffusion equations. The authors present in this paper the results of a comparison of five different linear solvers on a range of complex radiation and radiation-hydrodynamics problems. The linear solvers used are diagonally scaled conjugate gradient, GMRES with incomplete LU preconditioning, conjugate gradient with incomplete Cholesky preconditioning, multigrid, and multigrid-preconditioned conjugate gradient. These problems involve shock propagation, opacities varying over 5--6 orders of magnitude, tabular equations of state, and dynamic ALE (Arbitrary Lagrangian Eulerian) meshes. They perform a problem size scalability study by comparing linear solver performance over a wide range of problem sizes from 1,000 to 100,000 zones. The fundamental question they address in this paper is: Is it more efficient to invert the matrix in many inexpensive steps (like diagonally scaled conjugate gradient) or in fewer expensive steps (like multigrid)? In addition, what is the answer to this question as a function of problem size and is the answer problem dependent? They find that the diagonally scaled conjugate gradient method performs poorly with the growth of problem size, increasing in both iteration count and overall CPU time with the size of the problem and also increasing for larger time steps. For all problems considered, the multigrid algorithms scale almost perfectly (i.e., the iteration count is approximately independent of problem size and problem time step). For pure radiation flow problems (i.e., no hydrodynamics), they see speedups in CPU time of factors of {approx}15--30 for the largest problems, when comparing the multigrid solvers relative to diagonal scaled conjugate gradient.

Baldwin, C.; Brown, P.N.; Falgout, R.; Graziani, F.; Jones, J.

1999-09-01T23:59:59.000Z

229

Multiscale modeling of solar cells with interface phenomena  

E-Print Network [OSTI]

We describe a mathematical model for heterojunctions in semiconductors which can be used, e.g., for modeling higher efficiency solar cells. The continuum model involves well-known drift-diffusion equations posed away from the interface. These are coupled with interface conditions with a nonhomogeneous jump for the potential, and Robin-like interface conditions for carrier transport. The interface conditions arise from approximating the interface region by a lower-dimensional manifold. The data for the interface conditions are calculated by a Density Functional Theory (DFT) model over a few atomic layers comprising the interface region. We propose a domain decomposition method (DDM) approach to decouple the continuum model on subdomains which is implemented in every step of the Gummel iteration. We show results for CIGS/CdS, Si/ZnS, and Si/GaAs heterojunctions.

Foster, David H; Peszynska, Malgorzata; Schneider, Guenter

2013-01-01T23:59:59.000Z

230

ISIS++Reference Guide (Iterative Scalable Implicit Solver in C++) Version 1.1  

SciTech Connect (OSTI)

ISIS++ (Iterative Scalable Implicit Solver in C++) Version 1.1 is a portable, object-oriented framework for solving sparse linear systems of equations. It includes a collection of Krylov solution methods and preconditioners, as well as both uni-processor (serial) and multi-processor (scalable) matrix and vector classes. Though it was developed to solve systems of equations originating from large-scale, 3-D, finite element analyses, it has application in many other fields. This document supersedes the ISIS++ V1.0 Reference Guide, defines the V1. 1 interface specification, and includes the necessary instructions for building and running ISIS++ v 1.1 on Unix platforms. The interface is presented in annotated header format, along with background on design and implementation considerations. A finite difference modeling example problem is included to demonstrate the overall setup and use.

Alan B. Williams; Benjamin A. Allan; Kyran D. Mish; Robert L. Clay

1999-04-01T23:59:59.000Z

231

MELCOR ex-vessel LOCA simulations for ITER{sup +}  

SciTech Connect (OSTI)

Ex-vessel Loss-of-Coolant-Accident (LOCA) simulations for the International Thermonuclear Experimental Reactor (ITER) were performed using the MELCOR code. The main goals of this work were to estimate the ultimate pressurization of the heat transport system (HTS) vault in order to gauge the potential for stack releases and to estimate the total amount of hydrogen generated during a design basis ex-vessel LOCA. Simulation results indicated that the amount of hydrogen produced in each transient was below the flammability limit for the plasma chamber. In addition, only moderate pressurization of the HTS vault indicated a very small potential for releases through the stack.

Gaeta, M.J.; Merrill, B.J. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Bartels, H.W. [ITER San Diego Joint Work Site, La Jolla, CA (United States)] [and others

1995-11-01T23:59:59.000Z

232

Solitary Waves of the MRLW Equation by Variational Iteration Method  

SciTech Connect (OSTI)

In a recent publication, Soliman solved numerically the modified regularized long wave (MRLW) equation by using the variational iteration method (VIM). In this paper, corrected numerical results have been computed, plotted, tabulated, and compared with not only the exact analytical solutions but also the Adomian decomposition method results. Solitary wave solutions of the MRLW equation are exactly obtained as a convergent series with easily computable components. Propagation of single solitary wave, interaction of two and three waves, and also birth of solitons have been discussed. Three invariants of motion have been evaluated to determine the conservation properties of the problem.

Hassan, Saleh M. [Department of Mathematics, College of Science, King Saud University, P.O. Box 2455, Riyadh 11451 (Saudi Arabia); Department of Mathematics, College of Science, Ain Shams University, Abbassia 11566, Cairo (Egypt); Alamery, D. G. [Department of Mathematics, College of Science, King Saud University, P.O. Box 2455, Riyadh 11451 (Saudi Arabia)

2009-09-09T23:59:59.000Z

233

Status of the ITER IC H and CD System  

SciTech Connect (OSTI)

The ITER Ion Cyclotron Heating and Current Drive system will deliver 20 MW of radio frequency power to the plasma in quasi continuous operation during the different phases of the experimental programme. The system also has to perform conditioning of the tokamak first wall at low power between main plasma discharges. This broad range of requirements imposes a high flexibility and a high availability. The paper highlights the physics and design requirements on the IC system, the main features of its subsystems, the predicted performance, and the current procurement and installation schedule.

Lamalle, P. U.; Beaumont, B.; Gassmann, T.; Kazarian, F.; Arambhadiya, B.; Bora, D.; Jacquinot, J.; Mitteau, R.; Schueller, F. C.; Tanga, A. [ITER Organization, CS 90 046, 13067 Saint-Paul-Lez-Durance (France); Baruah, U.; Bhardwaj, A.; Kumar, R.; Mukherjee, A.; Singh, N. P.; Singh, R. [ITER India, A29, Sector 25, GIDC, Gandhinagar, Gujarat (India); Goulding, R.; Rasmussen, D.; Swain, D. [US ITER Project Office, Oak Ridge National Laboratory, P.O. Box 2008, 1055 CM, MS 6483, Oak Ridge, TN 37831-6483 (United States); Agarici, G. [Fusion for Energy, Josep Pla 2, 08019 Barcelona (Spain)] (and others)

2009-11-26T23:59:59.000Z

234

Volkov solution for two laser beams and ITER  

E-Print Network [OSTI]

We find the solution of the Dirac equation for two plane waves (laser beams) and we determine the modified Compton formula for the scattering of two photons on an alectron. The practical meaning of the two laser beams is, that two laser beams impinging on a targed which is constituted from material in the form of a foam, can replace 100-200 laser beams impinging on a normal targed. It means that the nuclear fusion with two laser beams is realistic in combination with the nuclear reactor such as ITER.

Miroslav Pardy

2005-07-12T23:59:59.000Z

235

U.S. ITER | Princeton Plasma Physics Lab  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest RegionatSearchScheduled SystemReleasesFeedback Provide‹ SeeITER

236

Iterative Krylov solution methods for geophysical electromagnetic simulations on throughput-oriented processing units  

E-Print Network [OSTI]

R. , 1992. Conjugate gradient type methods for linearand bi-conjugate gradient iterative methods to solve complexcase, the conjugate gradient (CG) method of Hestenes and

Commer, M.

2012-01-01T23:59:59.000Z

237

PPPL and ITER: Lab teams support the world's largest fusion experiment...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

port plugs inside the ITER tokamak. Included in the modular design are stainless steel components called diagnostic first walls that will directly face the plasma. These...

238

Flow distribution analysis on the cooling tube network of ITER thermal shield  

SciTech Connect (OSTI)

Thermal shield (TS) is to be installed between the vacuum vessel or the cryostat and the magnets in ITER tokamak to reduce the thermal radiation load to the magnets operating at 4.2K. The TS is cooled by pressurized helium gas at the inlet temperature of 80K. The cooling tube is welded on the TS panel surface and the composed flow network of the TS cooling tubes is complex. The flow rate in each panel should be matched to the thermal design value for effective radiation shielding. This paper presents one dimensional analysis on the flow distribution of cooling tube network for the ITER TS. The hydraulic cooling tube network is modeled by an electrical analogy. Only the cooling tube on the TS surface and its connecting pipe from the manifold are considered in the analysis model. Considering the frictional factor and the local loss in the cooling tube, the hydraulic resistance is expressed as a linear function with respect to mass flow rate. Sub-circuits in the TS are analyzed separately because each circuit is controlled by its own control valve independently. It is found that flow rates in some panels are insufficient compared with the design values. In order to improve the flow distribution, two kinds of design modifications are proposed. The first one is to connect the tubes of the adjacent panels. This will increase the resistance of the tube on the panel where the flow rate is excessive. The other design suggestion is that an orifice is installed at the exit of tube routing where the flow rate is to be reduced. The analysis for the design suggestions shows that the flow mal-distribution is improved significantly.

Nam, Kwanwoo; Chung, Wooho; Noh, Chang Hyun; Kang, Dong Kwon; Kang, Kyoung-O; Ahn, Hee Jae; Lee, Hyeon Gon [ITER Korea, National Fusion Research Institute, Daejeon 305-333 (Korea, Republic of)

2014-01-29T23:59:59.000Z

239

Solid breeder blanket option for the ITER conceptual design  

SciTech Connect (OSTI)

A solid-breeder water-cooled blanket option was developed for ITER based on a multilayer configuration. The blanket uses beryllium for neutron multiplication and lithium oxide for tritium breeding. The material forms are sintered products for both material with 0.8 density factor. The lithium-6 enrichment is 90%. This blanket has the capability to accommodate a factor of two change in the neutron wall loading without violating the different design guidelines. The design philosophy adopted for the blanket is to produce the necessary tritium required for the ITER operation and to operate at power reactor conditions as much as possible. At the same time, the reliability and the safety aspects of the blanket are enhanced by the use of a low-pressure coolant and the separation of the tritium purge lines from the coolant system. The blanket modules are made by hot vacuum forming and diffusion bonding a double wall structure with integral cooling channels. The different aspects of the blanket design including tritium breeding, nuclear heat deposition, activation analyses, thermal-hydraulics, tritium inventory, structural analyses, and water coolant conditions are summarized in this paper. 12 refs., 2 figs., 1 tab.

Gohar, Y.; Attaya, H.; Billone, M.C.; Finn, P.; Majumdar, S.; Turner, L.R.; Baker, C.C.; Nelson, B.E.; Raffray, R. (Argonne National Lab., IL (USA); Oak Ridge National Lab., TN (USA); California Univ., Los Angeles, CA (USA))

1989-10-01T23:59:59.000Z

240

Iterative image-domain decomposition for dual-energy CT  

SciTech Connect (OSTI)

Purpose: Dual energy CT (DECT) imaging plays an important role in advanced imaging applications due to its capability of material decomposition. Direct decomposition via matrix inversion suffers from significant degradation of image signal-to-noise ratios, which reduces clinical values of DECT. Existing denoising algorithms achieve suboptimal performance since they suppress image noise either before or after the decomposition and do not fully explore the noise statistical properties of the decomposition process. In this work, the authors propose an iterative image-domain decomposition method for noise suppression in DECT, using the full variance-covariance matrix of the decomposed images. Methods: The proposed algorithm is formulated in the form of least-square estimation with smoothness regularization. Based on the design principles of a best linear unbiased estimator, the authors include the inverse of the estimated variance-covariance matrix of the decomposed images as the penalty weight in the least-square term. The regularization term enforces the image smoothness by calculating the square sum of neighboring pixel value differences. To retain the boundary sharpness of the decomposed images, the authors detect the edges in the CT images before decomposition. These edge pixels have small weights in the calculation of the regularization term. Distinct from the existing denoising algorithms applied on the images before or after decomposition, the method has an iterative process for noise suppression, with decomposition performed in each iteration. The authors implement the proposed algorithm using a standard conjugate gradient algorithm. The method performance is evaluated using an evaluation phantom (Catphan©600) and an anthropomorphic head phantom. The results are compared with those generated using direct matrix inversion with no noise suppression, a denoising method applied on the decomposed images, and an existing algorithm with similar formulation as the proposed method but with an edge-preserving regularization term. Results: On the Catphan phantom, the method maintains the same spatial resolution on the decomposed images as that of the CT images before decomposition (8 pairs/cm) while significantly reducing their noise standard deviation. Compared to that obtained by the direct matrix inversion, the noise standard deviation in the images decomposed by the proposed algorithm is reduced by over 98%. Without considering the noise correlation properties in the formulation, the denoising scheme degrades the spatial resolution to 6 pairs/cm for the same level of noise suppression. Compared to the edge-preserving algorithm, the method achieves better low-contrast detectability. A quantitative study is performed on the contrast-rod slice of Catphan phantom. The proposed method achieves lower electron density measurement error as compared to that by the direct matrix inversion, and significantly reduces the error variation by over 97%. On the head phantom, the method reduces the noise standard deviation of decomposed images by over 97% without blurring the sinus structures. Conclusions: The authors propose an iterative image-domain decomposition method for DECT. The method combines noise suppression and material decomposition into an iterative process and achieves both goals simultaneously. By exploring the full variance-covariance properties of the decomposed images and utilizing the edge predetection, the proposed algorithm shows superior performance on noise suppression with high image spatial resolution and low-contrast detectability.

Niu, Tianye; Dong, Xue; Petrongolo, Michael; Zhu, Lei, E-mail: leizhu@gatech.edu [Nuclear and Radiological Engineering and Medical Physics Programs, The George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, Georgia 30332 (United States)] [Nuclear and Radiological Engineering and Medical Physics Programs, The George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, Georgia 30332 (United States)

2014-04-15T23:59:59.000Z

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

E-Print Network 3.0 - aerosol cfd model Sample Search Results  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Laboratory Collection: Engineering 14 Solution characters of iterative coupling between energy simulation and CFD programs Summary: type of airflow models. CFD predicts the...

242

Thermo-mechanical analysis of ITER first mirrors and its use for the ITER equatorial visible/infrared wide angle viewing system optical design  

SciTech Connect (OSTI)

ITER first mirrors (FMs), as the first components of most ITER optical diagnostics, will be exposed to high plasma radiation flux and neutron load. To reduce the FMs heating and optical surface deformation induced during ITER operation, the use of relevant materials and cooling system are foreseen. The calculations led on different materials and FMs designs and geometries (100 mm and 200 mm) show that the use of CuCrZr and TZM, and a complex integrated cooling system can limit efficiently the FMs heating and reduce their optical surface deformation under plasma radiation flux and neutron load. These investigations were used to evaluate, for the ITER equatorial port visible/infrared wide angle viewing system, the impact of the FMs properties change during operation on the instrument main optical performances. The results obtained are presented and discussed.

Joanny, M.; Salasca, S.; Dapena, M.; Cantone, B.; Travere, J. M. [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France); Thellier, C.; Ferme, J. J. [THALES SESO, 13593 Aix-en-Provence Cedex 3 (France); Marot, L. [Department of Physics, University of Basel, 4056 Basel (Switzerland); Buravand, O. [Institut d'Optique Graduate School, 91127 Palaiseau (France); Perrollaz, G. [AMETRA, 13770 Venelles (France); Zeile, C. [INR, KIT, D-76344 Eggenstein-Leopoldshafen (Germany)

2012-10-15T23:59:59.000Z

243

The Status of ITER; the ITER Design Review -G. Janeschitz -November 2007 Town Hall Meeting onTown Hall Meeting on ITERITER APS ConferenceAPS Conference  

E-Print Network [OSTI]

Temporary ITER Offices Building 519: occupied by ~ 150 (designed for 140 ­ 150) Extension Bureau: completed !Planning / Design !Integration / QA / Safety / Licensing / Schedule !Installation !Testing + Commissioning Design Review - G. Janeschitz - November 2007 7 Integrated Project Schedule (IPS) Basis - official10

244

Modified Visible and Infrared Optical Design for the ITER Upper Ports  

SciTech Connect (OSTI)

This document reports the results of a follow-on optical design study of visible-light and infrared optics for the ITER upper ports, performed by LLNL under contract for the US ITER Project Office. The major objectives of this work are to move the viewing aperture closer to the plasma so that the optical path does not cut through any adjacent blanket shield module other than the module designated for the port; move optics forward into the port tube to increase the aperture size and therefore improve the spatial resolution; assess the trade-off between spatial resolution and spatial coverage by reducing the field of view; and create a mechanical model with a neutron labyrinth. Here we show an optical design incorporating all these aspects. The new design fits into a 360 mm ID tube, as did the previous design. The entrance aperture is increased from 10 mm to 21 mm, with a corresponding increase in spatial resolution. The Airy disk diameter for 3.8 {micro}m wavelength IR light is 5.1 mm at the most distant target point in the field of view. The field of view is reduced from 60 toroidal degrees (full toroidal coverage with 6 cameras) to 50 toroidal degrees. The 10 degrees eliminated are those nearest the camera, which have the poorest view of the divertor plate and in fact saw little of the plate. The Cassegrain telescope that was outside the vacuum windows in the previous design is now in vacuum, along with lenses for visible light. The Cassegrain for visible light is eliminated. An additional set of optical relay lenses is added for the visible and for the IR.

Lasnier, C; Seppala, L; Morris, K

2008-04-24T23:59:59.000Z

245

Fusion Engineering and Design 46 (1999) 177183 ITER reference breeding blanket design  

E-Print Network [OSTI]

available from the Canadian heavy-water fission reactors. The ITER breeding blanket (BB) has to satisfy its The ITER reference breeding blanket design is water-cooled and is characterised by the use of the neutronic and SB modules have to adopt a common supply and supporting system, as well as the same installation

Raffray, A. René

246

Iterative methods for neutron transport eigenvalue Fynn Scheben and Ivan G. Graham  

E-Print Network [OSTI]

iterative methods for computing criticality in nuclear reactors. In general this requires the solution words. neutron transport, criticality, generalised eigenvalue problem, symmetry, inexact inverse iteration. AMS subject classifications. 45C05, 65F15, 65N25, 65R20, 65Z05, 82D75 1. Reactor criticality

Graham, Ivan

247

First ITER Council convened in Cadarache Historic step in the quest for clean Energy  

E-Print Network [OSTI]

First ITER Council convened in Cadarache Historic step in the quest for clean Energy Cadarache, 28 of age in a world in desperate need of clean, abundant, and carbon dioxide-free energy." Setting a new Energy Agency (IAEA), said: "Let me congratulate all who have contributed to the achievements of the ITER

248

A E Costley ITER Diagnostics, 21st IAEA of 5 slides  

E-Print Network [OSTI]

Costley ITER Diagnostics, 21st IAEA 2 of 5 slides PLAN Requirements for Plasma and First Wall MeasurementsA E Costley ITER Diagnostics, 21st IAEA 1 of 5 slides A E Costley1, C Walker2, L Bertalot2, R, Germany THE DESIGN AND IMPLEMENTATIONTHE DESIGN AND IMPLEMENTATION OF DIAGNOSTIC SYSTEMS ON ITEROF

249

S12.9Constrained Iterative Speech Enhance with Application to  

E-Print Network [OSTI]

S12.9Constrained Iterative Speech Enhance with Application to Automatic Speech Recognition John H Atlanta, GA 30332 set of iterative speech enhancement techniques employing spec- ral constraints. FinalIy, the enhancement algorithms are evaluated to determine their ability as preproces- and speech

Texas at Dallas, University of

250

Fusion Engineering and Design 81 (2006) 433441 An overview of US ITER test blanket module program  

E-Print Network [OSTI]

blankets: (1) a helium-cooled solid breeder concept with ferritic steel structure and Be neutron multiplierLi liquid breeder blanket concepts in ITER are identified. © 2005 Elsevier B.V. All rights reserved. Keywords: ITER test blanket module program; Helium-cooled solid breeder blanket; Dual-coolant lead

Abdou, Mohamed

2006-01-01T23:59:59.000Z

251

Soft-Input, Iterative, Reed-Solomon Decoding using Redundant Parity-Check Equations  

E-Print Network [OSTI]

approach to the iterative decoding of Reed-Solomon (RS) codes. The pre- sented methodology utilizesSoft-Input, Iterative, Reed-Solomon Decoding using Redundant Parity-Check Equations Jason Bellorado techniques is achievable with the presented methodology. The complexity of the proposed algorithm is orders

Kavcic, Aleksandar

252

FPA, Annual meeting, 3-4 December 2008 Slide 1 Status of ITER  

E-Print Network [OSTI]

FPA, Annual meeting, 3-4 December 2008 Slide 1 of 25 Status of ITER Fusion Power Associates Annual Organization #12;FPA, Annual meeting, 3-4 December 2008 Slide 2 of 25 Main Outline · History of ITER Project Program · External Relations · International School #12;FPA, Annual meeting, 3-4 December 2008 Slide 3

253

PISCES FY11 Research Highlight Tritium accumulation within the ITER vessel is expected to be dominated  

E-Print Network [OSTI]

PISCES FY11 Research Highlight Tritium accumulation within the ITER vessel is expected injected into the vessel. ITER has focused considerable effort into the ability to thermally remove tritium vessel. Another possible technique to mitigate tritium accumulation in these codeposited surfaces

254

Looking on bright side of losing ITER Risa Kato and Tetsuro Yamada / Yomiuri Shimbun Staff Writers  

E-Print Network [OSTI]

to have a remote-controlled ITER experiment unit, and one for the development of super heat candidate to have a remote-control facility is of especially high significance, according to experts. The remote-control facility is envisaged as playing a key role in the ITER project, as it will be able

255

A three-dimensional adaptive method based on the iterative grid redistribution  

E-Print Network [OSTI]

such as fluid dynamics, combustion and heat transfer and others, the required density of grid pointsA three-dimensional adaptive method based on the iterative grid redistribution Desheng Wang on iterative grid redistribution technique introduced in [J. Comput. Phys. 159 (2000) 246]. The key step

Wang, Desheng

256

Presented by Y.Shimomura ITER Joint Central Team and Home Teams  

E-Print Network [OSTI]

of reliability of the operation Full commissioning of the ITER systemin a non-nuclear environment DevelopmentPresented by Y.Shimomura ITER Joint Central Team and Home Teams Oct. 5, 2000 Sorrento, Italy #12 Elevation Layout #12;Phased Operations Hydrogen Phase Confirmation of the machine performance and increase

257

A Generalized Diffusion Based Inter-Iteration Nonlinear Bilateral Filtering Scheme for PET  

E-Print Network [OSTI]

A Generalized Diffusion Based Inter-Iteration Nonlinear Bilateral Filtering Scheme for PET Image inter-iteration filtering scheme based diffusion MAP estimate for PET image reconstruction is proposed,version1 #12;1. Introduction Positron emission tomography (PET) is one of the most important imaging tools

Paris-Sud XI, Université de

258

An iterative process for international negociations on acid rain in Northern Europe  

E-Print Network [OSTI]

An iterative process for international negociations on acid rain in Northern Europe using a general 138.48.4.14) #12; An iterative process for international negotiations on acid rain in Northern Europe transboundary pollution problem related to acid rain in Northern Europe. This simulation shows the need

Toint, Philippe

259

Fusion Power Associates Annual Meeting and Symposium Fusion Energy: Preparing for the NIF and ITER Era  

E-Print Network [OSTI]

Fusion Power Associates Annual Meeting and Symposium Fusion Energy: Preparing for the NIF and ITER of Directors 8:20 Presentation of Awards ­ S. Dean, President, FPA 8:30 Fusion at the Department of Energy Technology Program­ Stan Milora, ORNL 1:40 Issues and Opportunities from ITER Review ­ R. Hawryluk, PPPL 2

260

NESTED ITERATION AND FIRST-ORDER SYSTEM LEAST SQUARES FOR INCOMPRESSIBLE, RESISTIVE MAGNETOHYDRODYNAMICS  

E-Print Network [OSTI]

NESTED ITERATION AND FIRST-ORDER SYSTEM LEAST SQUARES FOR INCOMPRESSIBLE, RESISTIVE. This paper develops a nested iteration algorithm to solve time-dependent nonlinear systems of partial a sequence of nested spaces, where the resolution of the approximations increases as the algorithm progresses

McCormick, Steve

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

ISFNT-11, Barcelona, Spain, September 16-20, 2013 2013, ITER Organization  

E-Print Network [OSTI]

, Fabrication and Testing of the ITER First Wall and Shielding Blanket Presented by A. René Raffray Blanket Domestic Agency; 7SNL , US ITER Domestic Agency; 11th International Symposium on Fusion Nuclear Technology and neutron loads in the vacuum vessel and ex-vessel components · Provide a plasma-facing surface which

Raffray, A. René

262

Annual Report of the EURATOM/CCFE Fusion Programme 2010/11 8 ITER Systems  

E-Print Network [OSTI]

to the ITER heating, diagnostic and remote handling systems in particular. Fusion for Energy (F4E its substantial role in five key ITER systems: · Ion Cyclotron Resonance Heating (ICRH) system) content, the ion temperature and flow; · Remote handling system, in particular the design for the Neutral

263

Annual Report of the EURATOM/CCFE Fusion Programme 2013 8 ITER SYSTEMS  

E-Print Network [OSTI]

and undertake leading or major roles in the design and R&D of ITER specialist systems (Plasma Heating, Diagnostics and Remote Handling etc.). Seek to play other design roles in R&D of ITER specialist systems Resonance Heating (ICRH) system. Neutral Beam Injection heating system. Core LIDAR Thompson scattering

264

Annual Report of the EURATOM/CCFE Fusion Programme 2012/13 8 ITER SYSTEMS  

E-Print Network [OSTI]

Heating, Diagnostics and Remote Handling etc). · Seek to play other design roles in R&D of ITER specialist in the following key ITER systems: · Ion Cyclotron Resonance Heating (ICRH) system. · Neutral Beam Injection heating system. · Core LIDAR Thompson scattering to measure the electron temperature and density profiles

265

Nuclear systems and testing programs for ITER. Progress report for FY 1998  

SciTech Connect (OSTI)

The effort during this performance period focused on a number of TBWG activities (including test module design and analysis) that were identified and agreed upon (in the presence of the ITER Director and Deputy Director) at TBWG-4. These include: (a) DEMO test module design and performance analysis under pulsed operation; (b) Test program operation plan; (c) Test port design and analysis; (d) Decay heat calculations and safety analysis; (e) Further discussion among the parties to define collaboratory on R and D for the test program as well as possible collaboration on the construction and operation of test articles; (f) Remote handling and ancillary equipment; (g) Criteria for qualifying a blanket module or submodule for actual insertion and testing in ITER; (h) Definition of test module instrumentation and verification of capability to perform in the ITER fusion environment (magnetic field, radiation, heating, etc.); and (i) Analysis to show that the results to be obtained from the test modules as designed can be extrapolated to DEMO and reactor conditions (e.g., higher wall loads and the need to demonstrate tritium self-sufficiency). The main achievements during this performance period include: (1) updating and finalizing the US DDDs for the ITER Blanket Program to form part of the ITER Final Design Report (FDR). Specific revisions were in response to the minimal lithium volume test blanket design requirements and safety impact and (2) evaluating the feasibility of the US test program, including instrumentation and the benefits of the ITER test program. Details of this assessment, including solid breeder and liquid breeder blanket test plans, are documented in UCLA-IFNT-13 (attached). In addition, dose mapping calculations were performed for the ITER Building, including equipment and layout of coolant pipes/heat exchangers. A report on ITER Building dose calculations was sent to UD ITER management and to the Garching Task Coordinator in April, 1998. The report entitled Three-Dimensional Calculations of ITER Building Dose Rate Profiles and Assessment of Accessibility Inside the Building During Operation and After Shutdown of ITER can be located through ITER Reference Number of ITER Task S 62 TD 12, ID No: D325 ITER/US/98/S62TD12-D325 UCLA-FNT-100 UCLA-ENG-98-190.

NONE

1998-12-31T23:59:59.000Z

266

STUDENT EMPLOYMENT Student Involvement Outcomes  

E-Print Network [OSTI]

STUDENT EMPLOYMENT Student Involvement Outcomes reflective assessment High impact practices ASSOCIATED STUDENTS, CSUF, INC. Committed TO ON-CAMPUS ENGAGEMENT · SUPPORTING STUDENT SUCCESS · UNIFYING THE STUDENT VOICE · FOSTERING TITAN PRIDE #12;Organizational Structure Associated Students, CSUF, Inc. (ASI

de Lijser, Peter

267

Safety Analysis of the US Dual Coolant Liquid Lead-Lithium ITER Test Blanket Module  

SciTech Connect (OSTI)

The US is proposing a prototype of a dual coolant liquid lead-lithium (DCLL) DEMO blanket concept for testing in the International Thermonuclear Experimental Reactor (ITER) as an ITER Test Blanket Module (TBM). Because safety considerations are an integral part of the design process to ensure that this TBM does not adversely impact the safety of ITER, a safety assessment has been conducted for this TBM and its ancillary systems as requested by the ITER project. Four events were selected by the ITER International Team (IT) to address specific reactor safety concerns, such as VV pressurization, confinement building pressure build-up, TBM decay heat removal capability, tritium and activation products release from the TBM system, and hydrogen and heat production from chemical reactions. This paper summarizes the results of this safety assessment conducted with the MELCOR computer code.

Merrill, Brad; Reyes, Susana; Sawan, Mohamed; Wong, Clement

2006-07-01T23:59:59.000Z

268

Iterative Methods for Total Variation Image Restoration 1 Tony F. Chan 2 and Pep Mulet 3  

E-Print Network [OSTI]

. Moliner, 50, 46100 Burjas­ sot, Spain. Email: mulet@godella.matapl.uv.es. This author was also supported of an image usually involves a degradation process: a blurring, due to atmosphere turbulence, camera misfocus. The actual degradation model will depend on many factors, but a commonly used model is that of a linear

Chan, Tony F.

269

Linear iterative refinement method for the rapid simulation of borehole nuclear measurements: Part 2 --High-angle and horizontal wells  

E-Print Network [OSTI]

Linear iterative refinement method for the rapid simulation of borehole nuclear measurements: Part refinement method to rapidly simulate borehole nuclear measurements acquired in vertical wells neutron and density measurements. Based on new research, we implemented the linear iterative refinement

Torres-Verdín, Carlos

270

Iterative methods for dose reduction and image enhancement in tomography  

DOE Patents [OSTI]

A system and method for creating a three dimensional cross sectional image of an object by the reconstruction of its projections that have been iteratively refined through modification in object space and Fourier space is disclosed. The invention provides systems and methods for use with any tomographic imaging system that reconstructs an object from its projections. In one embodiment, the invention presents a method to eliminate interpolations present in conventional tomography. The method has been experimentally shown to provide higher resolution and improved image quality parameters over existing approaches. A primary benefit of the method is radiation dose reduction since the invention can produce an image of a desired quality with a fewer number projections than seen with conventional methods.

Miao, Jianwei; Fahimian, Benjamin Pooya

2012-09-18T23:59:59.000Z

271

Ideal MHD Stability of ITER Steady State Scenarios with ITBs  

SciTech Connect (OSTI)

One of ITER goals is to demonstrate feasibility of continuous operations using non-inductive current drive. Two main candidates have been identified for advanced operations: the long duration, high neutron fluency hybrid scenario and the steady state scenario, both operating at a plasma current lower than the reference ELMy scenario [1][2] to minimize the required current drive. The steady state scenario targets plasmas with current 7-10 MA in the flat-top, 50% of which will be provided by the self-generated, pressure-driven bootstrap current. It has been estimated that, in order to obtain a fusion gain Q > 5 at a current of 9 MA, it should be ?N > 2.5 and H > 1.5 [3]. This implies the presence of an Internal Transport Barrier (ITB). This work discusses how the stability of steady state scenarios with ITBs is affected by the external heating sources and by perturbations of the equilibrium profiles.

F.M. Poli, C.E. Kessel, S. Jardin, J. Manickam, M. Chance, J. Chen

2011-07-27T23:59:59.000Z

272

DESIGN OF THE ITER IN-VESSEL COILS  

SciTech Connect (OSTI)

The ITER project is considering the inclusion of two sets of in-vessel coils, one to mitigate the effect of Edge Localized Modes (ELMs) and another to provide vertical stabilization (VS). The in-vessel location (behind the blanket shield modules, mounted to the vacuum vessel inner wall) presents special challenges in terms of nuclear radiation (~3000 MGy) and temperature (100oC vessel during operations, 200oC during bakeout). Mineral insulated conductors are well suited to this environment but are not commercially available in the large cross section required. An R&D program is underway to demonstrate the production of mineral insulated (MgO or Spinel) hollow copper conductor with stainless steel jacketing needed for these coils. A preliminary design based on this conductor technology has been developed and is presented herein.

Neumeyer, C; Bryant, L; Chrzanowski, J; Feder, R; Gomez, M; Heitzenroeder, P; Kalish, M; Lipski, A; Mardenfeld, M; Simmons, R; Titus, P; Zatz, I; Daly, E; Martin, A; Nakahira, M; Pillsbury, R; Feng, J; Bohm, T; Sawan, M; Stone, H; Griffiths, I

2010-11-27T23:59:59.000Z

273

Status of ITER neutral beam cell remote handling system  

E-Print Network [OSTI]

The ITER neutral beam cell will contain up to three heating neutral beams and one diagnostic neutral beam, and four upper ports. Though manual maintenance work is envisaged within the cell, when containment is breached, or the radiological protection is removed the maintenance must be conducted remotely. This maintenance constitutes the removal and replacement of line replaceable units, and their transport to and from a cask docked to the cell. A design of the remote handling system has been prepared to concept level which this paper describes including the development of a beam line transporter, beam source remote handling equipment, upper port remote handling equipment and equipment for the maintenance of the neutral shield. This equipment has been developed complete the planned maintenance tasks for the components of the neutral beam cell and to have inherent flexibility to enable as yet unforeseen tasks and recovery operations to be performed.

Sykes, N; Choi, C-H; Crofts, O; Crowe, R; Damiani, C; Delavalle, S; Meredith, L; Mindham, T; Raimbach, J; Tesini, A; Van Uffelen, M

2013-01-01T23:59:59.000Z

274

Development of the bus joint for the ITER Central Solenoid  

SciTech Connect (OSTI)

The terminations of the Central Solenoid (CS) modules are connected to the bus extensions by joints located outside the CS in the gap between the CS and Torodial Field (TF) assemblies. These joints have very strict space limitations. Low resistance is a common requirement for all ITER joints. In addition, the CS bus joints will experience and must be designed to withstand significant variation in the magnetic field of several tenths of a Tesla per second during initiation of plasma. The joint resistance is specified to be less than 4 nOhm. The joints also have to be soldered in the field and designed with the possibility to be installed and dismantled in order to allow cold testing in the cold test facility. We have developed coaxial joints that meet these requirements and have demonstrated the feasibility to fabricate and assemble them in the vertical configuration. We introduced a coupling cylinder with superconducting strands soldered to the surface of the cable that can be installed in the ITER assembly hall and at the Cold Test Facility. This cylinder serves as a transition area between the CS module and the bus extension. We made two racetrack samples and tested four bus joints in our Joint Test Apparatus. Resistance of the bus joints was measured by a decay method and by a microvoltmeter; the value of the current was measured by the Hall probes. This measurement method was verified in the previous tests. The resistance of the joints varied insignificantly from 1.5 to 2 nOhm. One of the challenges associated with a soldered joint is the inability to use corrosive chemicals that are difficult to clean. This paper describes our development work on cable preparation, chrome removal, compaction, soldering, and final assembly and presents the test results.

Martovetsky, Nicolai N [ORNL] [ORNL; Irick, David Kim [ORNL] [ORNL; Kenney, Steven J [ORNL] [ORNL

2013-01-01T23:59:59.000Z

275

Evolution of Plasma Parameters in the Termination Phase of High Confinement H-modes at JET and Implications for ITER  

E-Print Network [OSTI]

Evolution of Plasma Parameters in the Termination Phase of High Confinement H-modes at JET and Implications for ITER

276

Reconstruction of Distribution Functions of Fast Ions and Runaway Electrons in ITER Plasmas Using Gamma-Ray Spectrometry  

E-Print Network [OSTI]

Reconstruction of Distribution Functions of Fast Ions and Runaway Electrons in ITER Plasmas Using Gamma-Ray Spectrometry

277

High-Energy Fuel Ion Diagnostics on ITER Derived from Neutron Emission Spectroscopy Measurements on JET DT Plasmas  

E-Print Network [OSTI]

High-Energy Fuel Ion Diagnostics on ITER Derived from Neutron Emission Spectroscopy Measurements on JET DT Plasmas

278

Analysis of Rotating Collectors from the Private Region of JET with Carbon Wall and Metallic ITER-Like Wall  

E-Print Network [OSTI]

Analysis of Rotating Collectors from the Private Region of JET with Carbon Wall and Metallic ITER-Like Wall

279

The ITERThe ITER eraera : the 10: the 10 yearyear roadmaproadmap for the French fusion programmefor the French fusion programme  

E-Print Network [OSTI]

-2035 : The Fusion Energy Era of magnetic fusion research ITER thermonuclear plasmasITER thermonuclear plasmasThe ITERThe ITER eraera : the 10: the 10 yearyear roadmaproadmap for the French fusion programmefor the French fusion programme E. Tsitrone1 on behalf of IRFM and Tore Supra team 1 : CEA, IRFM, F-13108 Saint

280

Political Involvement and Electoral Competition  

E-Print Network [OSTI]

Annual Review of Political Science, 7, pp. 25-46. Kendall,Conway, M. Margaret. 2000. Political participation in theand O. Listhaug. 1995. Political Sophistication and Models

De Sio, Lorenzo

2006-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Formation and Sustainment of ITPs in ITER with the Baseline Heating Mix  

SciTech Connect (OSTI)

Plasmas with internal transport barriers (ITBs) are a potential and attractive route to steady-state operation in ITER. These plasmas exhibit radially localized regions of improved con nement with steep pressure gradients in the plasma core, which drive large bootstrap current and generate hollow current pro les and negative shear. This work examines the formation and sustainment of ITBs in ITER with electron cyclotron heating and current drive. It is shown that, with a trade-o of the power delivered to the equatorial and to the upper launcher, the sustainment of steady-state ITBs can be demonstrated in ITER with the baseline heating con guration.

Francesca M. Poli and Charles Kessel

2012-12-03T23:59:59.000Z

282

RF-sheath heat flux estimates on Tore Supra and JET ICRF antennae. Extrapolation to ITER  

SciTech Connect (OSTI)

RF-sheath induced heat loads are identified from infrared thermography measurements on Tore Supra ITER-like prototype and JET A2 antennae, and are quantified by fitting thermal calculations. Using a simple scaling law assessed experimentally, the estimated heat fluxes are then extrapolated to the ITER ICRF launcher delivering 20 MW RF power for several plasma scenarios. Parallel heat fluxes up to 6.7 MW/m{sup 2} are expected very locally on ITER antenna front face. The role of edge density on operation is stressed as a trade-off between easy RF coupling and reasonable heat loads. Sources of uncertainty on the results are identified.

Colas, L.; Portafaix, C.; Goniche, M. [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France); Jacquet, Ph. [EURATOM/UKAEA Fusion Association, Culham, OX14 3DB (United Kingdom); Agarici, G. [Fusion for Energy, C/Josep Pla 2, E-08019 Barcelona (Spain)

2009-11-26T23:59:59.000Z

283

Status of the Design of the ITER ECE Diagnostic  

SciTech Connect (OSTI)

The baseline design for the ITER electron cyclotron emission (ECE) diagnostic has entered the detailed preliminary design phase. Two plasma views are planned, a radial view and an oblique view that is sensitive to distortions in the electron momentum distribution near the average thermal momentum. Both views provide high spatial resolution electron temperature profiles when the momentum distribution remains Maxwellian. The ECE diagnostic system consists of the front-end optics, including two 1000 K calibration sources, in equatorial port plug EP9, the 70-1000 GHz transmission system from the front-end to the diagnostics hall, and the ECE instrumentation in the diagnostics hall. The baseline ECE instrumentation will include two Michelson interferometers that can simultaneously measure ordinary and extraordinary mode ECE from 70 to 1000 GHz, and two heterodyne radiometer systems, covering 122-230 GHz and 244-355 GHz. Significant design challenges include 1) developing highly-reliable 1000 K calibration sources and the associated shutters/mirrors, 2) providing compliant couplings between the front-end optics and the polarization splitter box that accommodate displacements of the vacuum vessel during plasma operations and bake out, 3) protecting components from damage due to stray ECH radiation and other intense millimeter wave emission and 4) providing the low-loss broadband transmission system.

Taylor, Gary [PPPL

2014-04-01T23:59:59.000Z

284

An assessment of the base blanket for ITER  

SciTech Connect (OSTI)

Ideally, the ITER base blanket would provide the necessary tritium for the reactor to be self-sufficient during operation, while having minimal impact on the overall reactor cost, reliability and safety. A solid breeder blanket has been developed in CDA phase in an attempt to achieve such objectives. The reference solid breeder base blanket configurations at the end of the CDA phase has many attractive features such as a tritium breeding ratio (TBR) of 0.8--0.9 and a reasonably low tritium inventory. However, some concerns regarding the risk, cost and benefit of the base blanket have been raised. These include uncertainties associated with the solid breeder thermal control and the potentially high cost of the amount of Be used to achieve high TBR and to provide the necessary thermal barrier between the high temperature solid breeder and low temperature coolant. This work addresses these concerns. The basis for the selection of a breeding blanket is first discussed in light of the incremental risk, cost and benefits relative to a non-breeding blanket. Key issues associated with the CDA breeding blanket configurations are then analyzed. Finally, alternative schemes that could enhance the attractiveness and flexibility of a breeding blanket are explored.

Raffray, A.R.; Abdou, M.A.; Ying, A.

1991-01-01T23:59:59.000Z

285

Helium-cooled solid breeder blanket for ITER  

SciTech Connect (OSTI)

This paper summarizes the latest results of a design study of a helium-cooled solid breeder blanket for ITER. Attractive features of this design include the following: (1) There is a significant design margin since only part of the allowable solid breeder temperature window needs to be used. (2) There is an expanding data base available from solid breeder experiments carried out internationally. (3) The solid breeder can be designed to operate at high reactor-relevant temperature, while the helium is kept at moderate temperature and pressure for safety and reliability. In addition, since helium is a gas, it can be run so as to optimize the structure temperature and accommodate long term power variation without incurring any substantial pressure penalty. (4) The use of helium, an inert gas minimizing any chemical reaction and corrosion, in combination with a low activation solid breeder, is a safety advantage. An extensive list of the blanket operating parameters is provided and key factors are discussed.

Raffray, A.R.; Abdou, M.A.; Chou, P.; Gorbis, Z.; Tillack, M.; Watanabe, Y.; Ying, A.

1989-03-01T23:59:59.000Z

286

An Overview of the US DCLL ITER-TBM Program  

SciTech Connect (OSTI)

Under the US Fusion Nuclear Science and Technology program, we selected the Dual Coolant Lead Lithium (DCLL) concept as our primary Test Blanket Module (TBM) for testing in ITER. The DCLL blanket concept has the potential to be a high-performance DEMO blanket design with a projected thermal efficiency of >40%. Reduced activation ferritic/martensitic (RAF/M) steel is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled Pb-17Li breeder is circulated for power conversion and for tritium extraction. A SiC-based flow channel insert (FCI) is used as an electrical insulator for magnetohydrodynamic pressure drop reduction from the circulating Pb-17Li and as a thermal insulator to separate the high-temperature Pb-17Li (650–700 °C) from the RAF/M structure, which has a corrosion temperature limit of 480 °C. The RAF/M material must also operate at temperatures above 350 °C but less than 550 °C. We are continuing the development of the mechanical design and performing neutronics, structural and thermal hydraulics analyses of the DCLL TBM module. Prototypical FCI structures were fabricated and further attention was paid to MHD effects and the design of the inboard blanket for DEMO. We are also making progress on related R&D needs to address key areas. This paper is a summary report on the progress and results of recent DCLL TBM development activities.

C.P.C. Wong; M. Abdou; M. Dagher; Y. Katoh; B. J. Merrill

2010-12-01T23:59:59.000Z

287

An overview of the US DCLL ITER-TBM program  

SciTech Connect (OSTI)

Under the US Fusion Nuclear Science and Technology program, we selected the Dual Coolant Lead Lithium (DCLL) concept as our primary Test Blanket Module (TBM) for testing in ITER. The DCLL blanket concept has the potential to be a high-performance DEMO blanket design with a projected thermal ef?ciency of >40%. Reduced activation ferritic/martensitic (RAF/M) steel is used as the structural material. Helium is used to cool the ?rst wall and blanket structure, and the self-cooled Pb-17Li breeder is circulated for power conversion and for tritium extraction. A SiC-based ?ow channel insert (FCI) is used as an electrical insulator for magnetohydrodynamic pressure drop reduction from the circulating Pb-17Li and as a ther- mal insulator to separate the high-temperature Pb-17Li (?650–700 ? C) from the RAF/M structure, which has a corrosion temperature limit of ?480 ? C. The RAF/M material must also operate at temperatures above 350 ? C but less than 550 ? C. We are continuing the development of the mechanical design and per- forming neutronics, structural and thermal hydraulics analyses of the DCLL TBM module. Prototypical FCI structures were fabricated and further attention was paid to MHD effects and the design of the inboard blanket for DEMO. We are also making progress on related R&D needs to address key areas. This paper is a summary report on the progress and results of recent DCLL TBM development activities.

Wong, Clement; Abdou, Mohamed A.; Dagher, Mohamad; Katoh, Yutai; Kurtz, Richard J.; Malang, S.; Marriott, Edward P.; Merrill, Brad; Messadek, Karim; Morley, Neil; Sawan, M.; Sharafat, Shahran; Smolentsev, S.; Sze, Dai Kai; Willms, Scott; Ying, A. Y.; Youssef, M.

2010-12-01T23:59:59.000Z

288

An Overview of the US DCLL ITER TBM Program  

SciTech Connect (OSTI)

Under the US Fusion Nuclear Science and Technology program, we selected the Dual Coolant Lead Lithium (DCLL) concept as our primary Test Blanket Module (TBM) for testing in ITER. The DCLL blanket concept has the potential to be a high-performance DEMO blanket design with a projected thermal efficiency of >40%. Reduced activation ferritic/martensitic (RAF/M) steel is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled Pb-17Li breeder is circulated for power conversion and for tritium extraction. A SiC-based flow channel insert (FCI) is used as an electrical insulator for magnetohydrodynamic pressure drop reduction from the circulating Pb-17Li and as a thermal insulator to separate the high-temperature Pb-17Li ({approx}650-700 C) from the RAF/M structure, which has a corrosion temperature limit of {approx}480 C. The RAF/M material must also operate at temperatures above 350 C but less than 550 C. We are continuing the development of the mechanical design and performing neutronics, structural and thermal hydraulics analyses of the DCLL TBM module. Prototypical FCI structures were fabricated and further attention was paid to MHD effects and the design of the inboard blanket for DEMO. We are also making progress on related R&D needs to address key areas. This paper is a summary report on the progress and results of recent DCLL TBM development activities.

Wong, C. P. C. [General Atomics, San Diego; Abdou, M [University of California, Los Angeles; Dagher, M [University of California, Los Angeles; Katoh, Yutai [ORNL; Kurtz, Richard [Pacific Northwest National Laboratory (PNNL); Malang, Siegfried [Consultant; Marriott, Edward [University of Wisconsin, Madison; Merrill, Brad [Idaho National Laboratory (INL); Messadek, K [University of California, Los Angeles; Morley, N.B. [University of California, Los Angeles; Pint, Bruce A [ORNL; Sawan, M. [University of Wisconsin; Sharafat, S [University of California, Los Angeles; Smolentsev, Sergey [University of California, Los Angeles; Sze, Dai-Kai [University of California, San Diego; Willms, Scott [Los Alamos National Laboratory (LANL); Ying, Alice [University of California, Los Angeles; Youssef, M Z [University of California, Los Angeles

2010-01-01T23:59:59.000Z

289

An assessment of the base blanket for ITER  

SciTech Connect (OSTI)

Ideally, the ITER base blanket would provide the necessary tritium for the reactor to be self-sufficient during operation, while having minimal impact on the overall reactor cost, reliability and safety. A solid breeder blanket has been developed in CDA phase in an attempt to achieve such objectives. The reference solid breeder base blanket configurations at the end of the CDA phase has many attractive features such as a tritium breeding ratio (TBR) of 0.8--0.9 and a reasonably low tritium inventory. However, some concerns regarding the risk, cost and benefit of the base blanket have been raised. These include uncertainties associated with the solid breeder thermal control and the potentially high cost of the amount of Be used to achieve high TBR and to provide the necessary thermal barrier between the high temperature solid breeder and low temperature coolant. This work addresses these concerns. The basis for the selection of a breeding blanket is first discussed in light of the incremental risk, cost and benefits relative to a non-breeding blanket. Key issues associated with the CDA breeding blanket configurations are then analyzed. Finally, alternative schemes that could enhance the attractiveness and flexibility of a breeding blanket are explored.

Raffray, A.R.; Abdou, M.A.; Ying, A.

1991-12-31T23:59:59.000Z

290

Attachment to Joint Declaration of the Ministerial Meeting for ITER Moscow, 28th  

E-Print Network [OSTI]

centre for fusion science a centre for remote experimentation - Fusion power plant technology co include: - IFMIF (EVEDA and/or facility) - ITER research centre(s): including, a computational simulation

291

Iterative nonlinear beam propagation method and its application in nonlinear devices  

E-Print Network [OSTI]

In this thesis, an iterative nonlinear beam propagation method is introduced and applied to optical devices. This method is based on Hamiltonian ray tracing and the Wigner distribution function. First, wave propagation ...

Gao, Hanhong

2011-01-01T23:59:59.000Z

292

BPO Inputs to ITER Design Review on Pellet Pacing, RMP and RWM Coils,  

E-Print Network [OSTI]

by Energy Loss · Loarte estimated the maximum fueling rate consistent with a convective power loss to ITER. · Convective power loss constrains to 5.4 1022 atoms/s consistent with Q=10 performance. #12;A

293

Annual Report of the EURATOM/UKAEA Fusion Programme 2006/07 8 ITER and IFMIF  

E-Print Network [OSTI]

of the International Fusion Materials Irradiation Facility (IFMIF), the main facility other than ITER that is needed.1), the components in the plug and the remainder of the systems (relay optics etc to areas with detectors

294

Calculation and measurement of higher order mode losses in ITER ECH transmission lines  

E-Print Network [OSTI]

The ITER transmission lines (TLs) must be designed to deliver 20 MW from a 24 MW, 170 GHz gyrotron system. Miter bends are the main source of loss for these highly overmoded, corrugated, cylindrical waveguide TLs. Previous ...

Temkin, Richard J.

295

Iterative equalization and decoding using reduced-state sequence estimation based soft-output algorithms  

E-Print Network [OSTI]

We study and analyze the performance of iterative equalization and decoding (IED) using an M-BCJR equalizer. We use bit error rate (BER), frame error rate simulations and extrinsic information transfer (EXIT) charts to study and compare...

Tamma, Raja Venkatesh

2004-09-30T23:59:59.000Z

296

Tritium inventory control in ITER Charles Skinner with key contributions from  

E-Print Network [OSTI]

Tritium inventory control in ITER Charles Skinner with key contributions from Charles Gentile permitted" Tritium inventory control Worrisome issue: Once at the tritium limit there won't be any more

Princeton Plasma Physics Laboratory

297

robustly minimal iterated function systems Department of Mathematics, Ferdowsi University of Mashhad, Iran  

E-Print Network [OSTI]

University of Mashhad, Iran f h ghane@yahoo.com A.J. Homburg Korteweg-de Vries Institute for Mathematics University of Mashhad, Iran ali.sarizadeh@gmail.com August 6, 2009 Abstract We construct iterated function

Homburg, Ale Jan

298

The European Joint Undertaking for ITER and the Development of Fusion Energy  

E-Print Network [OSTI]

· Manage procurement and Quality Assurance · Arrange to make European staff available to ITER · Interface · Transparency ­ decision making process and Financial Regulation rules · Synergy and Complementarity

299

Design and RF measurements of a 5 GHz 500 kW window for the ITER LHCD system  

E-Print Network [OSTI]

CEA/IRFM is conducting R\\&D efforts in order to validate the critical RF components of the 5 GHz ITER LHCD system, which is expected to transmit 20 MW of RF power to the plasma. Two 5 GHz 500 kW BeO pill-box type window prototypes have been manufactured in 2012 by the PMB Company, in close collaboration with CEA/IRFM. Both windows have been validated at low power, showing good agreement between measured and modeling, with a return loss better than 32 dB and an insertion loss below 0.05 dB. This paper reports on the window RF design and the low power measurements. The high power tests up to 500kW have been carried out in March 2013 in collaboration with NFRI. Results of these tests are also reported. In the current ITER LHCD design, 20 MW Continuous Wave (CW) of Radio-Frequency power at 5 GHz are expected to be generated and transmitted to the plasma. In order to separate the vacuum vessel pressure from the cryostat waveguide pressure, forty eight 5 GHz 500kW CW windows are to be assembled on the waveguide...

Hillairet, Julien; Dechambre, N; Delpech, L; Ekedahl, A; Faure, N; Goniche, M; Kim, J; Larroque, S; Magne, R; Marfisi, L; Namkung, W; Park, H; Park, S; Poli, S; Vulliez, K

2015-01-01T23:59:59.000Z

300

ITER as a Physics Experiment K.Lackner, D. Campbell and many others  

E-Print Network [OSTI]

: -> only full CD,ELMy H-mode cases shown JT-60U RS JT-60U high bp ITER & Power Plant: higher n-mode access, ELMs, NTMs..) · qualify a-particle heating as a heating method · high power/long pulse (on wall of sawteeth (JET) AUG DIII- D #12;Q =10: ITER-simulation discharges on JET JET-operating space #12;Q =10

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Vacuum photodiode detectors for soft x-ray ITER plasma tomography  

SciTech Connect (OSTI)

A special type of vacuum photodiode detector (VPD) for x-ray tomography of (ITER) plasma is described. Laboratory experiments demonstrate that VPD has high sensitivity to thermal x-rays and low sensitivity to hard gamma rays and neutrons. It was shown that in ITER environment the signal due to thermal x-rays will surpass the background signal by more than a factor of 100.

Gott, Yu.V.; Stepanenko, M.M. [RRC, Nuclear Fusion Institute, Kurchatov sq.1, Moscow, 123182 (Russian Federation)

2005-07-15T23:59:59.000Z

302

Qualification of the US made conductors for ITER TF magnet system  

SciTech Connect (OSTI)

The US Domestic Agency (USDA) is one of the six suppliers of the TF conductor for ITER. In order to qualify conductors according to ITER requirements we prepared several lengths of the CICC and short samples for testing in the SULTAN facility in CRPP, Switzerland. We also fully characterized the strands that were used in these SULTAN samples. Fabrication experience and test results are presented and discussed.

Martovetsky, N; Hatfield, D; Miller, J; Bruzzone, P; Stepanov, B; Seber, B

2009-10-08T23:59:59.000Z

303

Toroidal field coil replacement study for the International Thermonuclear Experimental Reactor (ITER)  

SciTech Connect (OSTI)

The objective of this study is to develop an estimate of the time required to replace a failed toroidal field (TF) coil in the International Thermonuclear Experimental Reactor (ITER). This estimate is based on the current ITER design which resulted from the Conceptual Design Activities began in spring of 1988 and ending in December 1990. Although the TF Coils in ITER are designated permanent components and expected to last the life of the plant, the history of failures of large coils in fusion devices has prompted an assessment of the down time that might be required for replacement of a failed TF coil in ITER. The difficulty of replacement of a TF Coil in ITER is compounded by the large physical size of ITER, and the radiation fields which necessitate the use of remote handling equipment for most maintenance activities. Since 10 out of 16 TF coils are adjacent to either a Neutral Beam Injector (NBI) port or a remote handling (RH) port, it is probable that a failed TF Coil will be in one of these inconvenient locations. For this study, TF coil number 3 is assumed to fail and its replacement will be evaluated as a typical case. TF coil number 3 is located between a remote handling port ({number sign}3) and a port allocated to the lower hybrid ({number sign}4).

Not Available

1991-08-01T23:59:59.000Z

304

Toroidal field coil replacement study for the International Thermonuclear Experimental Reactor (ITER)  

SciTech Connect (OSTI)

The objective of this study is to develop an estimate of the time required to replace a failed toroidal field (TF) coil in the International Thermonuclear Experimental Reactor (ITER). This estimate is based on the current ITER design which resulted from the Conceptual Design Activities began in spring of 1988 and ending in December 1990. Although the TF Coils in ITER are designated permanent components and expected to last the life of the plant, the history of failures of large coils in fusion devices has prompted an assessment of the down time that might be required for replacement of a failed TF coil in ITER. The difficulty of replacement of a TF Coil in ITER is compounded by the large physical size of ITER, and the radiation fields which necessitate the use of remote handling equipment for most maintenance activities. Since 10 out of 16 TF coils are adjacent to either a Neutral Beam Injector (NBI) port or a remote handling (RH) port, it is probable that a failed TF Coil will be in one of these inconvenient locations. For this study, TF coil number 3 is assumed to fail and its replacement will be evaluated as a typical case. TF coil number 3 is located between a remote handling port ({number_sign}3) and a port allocated to the lower hybrid ({number_sign}4).

Not Available

1991-08-01T23:59:59.000Z

305

FEMCAM Analysis of SULTAN Test Results for ITER Nb3SN Cable-conduit Conductors  

SciTech Connect (OSTI)

Performance degradation due to filament fracture of Nb3 Sn cable-in-conduit conductors (CICCs) is a critical issue in large-scale magnet designs such as ITER which is currently being constructed in the South of France. The critical current observed in most SULTAN TF CICC samples is significantly lower than expected and the voltage-current characteristic is seen to have a much broader transition from a single strand to the CICC. Moreover, most conductors exhibit the irreversible degradation due to filament fracture and strain relaxation under electromagnetic cyclic loading. With recent success in monitoring thermal strain distribution and its evolution under the electromagnetic cyclic loading from in situ measurement of critical temperature, we apply FEMCAM which includes strand filament breakage and local current sharing effects to SULTAN tested CICCs to study Nb3 Sn strain sensitivity and irreversible performance degradation. FEMCAM combines the thermal bending effect during cool down and the EM bending effect due to locally accumulating Lorentz force during magnet operation. It also includes strand filament fracture and related local current sharing for the calculation of cable n value. In this paper, we model continuous performance degradation under EM cyclic loading based on strain relaxation and the transition broadening upon cyclic loading to the extreme cases seen in SULTAN test data to better quantify conductor performance degradation.

Yuhu Zhai, Pierluigi Bruzzone, Ciro Calzolaio

2013-03-19T23:59:59.000Z

306

An Iterative Algorithm for Battery-Aware Task Scheduling on Portable Computing Platforms  

E-Print Network [OSTI]

In this work we consider battery powered portable systems which either have Field Programmable Gate Arrays (FPGA) or voltage and frequency scalable processors as their main processing element. An application is modeled in the form of a precedence task graph at a coarse level of granularity. We assume that for each task in the task graph several unique design-points are available which correspond to different hardware implementations for FPGAs and different voltage-frequency combinations for processors. It is assumed that performance and total power consumption estimates for each design-point are available for any given portable platfrom, including the peripheral components such as memory and display power usage. We present an iterative heuristic algorithm which finds a sequence of tasks along with an appropriate design-point for each task, such that a deadline is met and the amount of battery energy used is as small as possible. A detailed illustrative example along with a case study of a real-world applicati...

Khan, Jawad

2011-01-01T23:59:59.000Z

307

Nonparametric GARCH Models Peter Buhlmann  

E-Print Network [OSTI]

Nonparametric GARCH Models Peter Buhlmann #3; Seminar fur Statistik Federal Institute describe a nonparametric GARCH model of #12;rst order and pro- pose a simple iterative algorithm for its GARCH(1,1) modelling, particularly when asymmetries are present in the data. We show how the basic

McNeil, Alexander J.

308

Hybrid Diverter Sheath Model Jeff Hammel  

E-Print Network [OSTI]

Hybrid Diverter Sheath Model Jeff Hammel Plasma Theory and Simulation Group APS ­ Division using a particle-fluid hybrid model. Electrons are modeled as an inertia-less (Boltzmann) fluid gyrokinetic code. The modeling methodology for the iterative nonlinear solver is presented. The hybrid model

Wurtele, Jonathan

309

ITER Building Design (D230-B), Task No. 28. Final report  

SciTech Connect (OSTI)

The International Thermonuclear Experimental Reactor (ITER) Project requires a set of buildings, each with its own distinct function, to support ITER`s mission. The Joint Central Team (JCT) has identified all the buildings in the set and has placed them in an efficient arrangement on the site. The JCT has developed a conceptual layout of each individual building. The buildings have been categorized into two main groups: (1) {open_quotes}Level 1 Buildings{close_quotes} which are on the construction schedule critical path and (2) {open_quotes}Level 2 Buildings{close_quotes} which, while important, are not on the critical path. The buildings are further categorized according to construction material, that is, {open_quotes}reinforced concrete{close_quotes} or {open_quotes}steel-frame on concrete slab{close_quotes}. This Report responds to the Project`s request to perform the initial structural steel design for all the {open_quotes}steel-frame on concrete slab{close_quotes} buildings. Of the twelve (12) {open_quotes}steel-frame on concrete slab{close_quotes} buildings, four (4) are Level 1 and eight (8) are Level 2 Buildings. This Report is a deliverable for the ITER Task Assignment entitled {open_quotes}ITER Buildings Design (D230-B){close_quotes}, also designated as Task No. 28. ITER U.S. Home Team Industrial Consortium members, Raytheon Engineers & Constructors (RE&C) and Stone & Webster Engineering Corporation (SWEC), teamed to perform Task 28. This task commenced in May 1995. It was performed in accordance with the design criteria specified by the ITER-JCT, San Diego Joint Work Site.

NONE

1995-12-01T23:59:59.000Z

310

Exhibit 1C Patent Rights Retention by the Seller ITER UT-B Contracts Div Page 1 of 5  

E-Print Network [OSTI]

Exhibit 1C ­ Patent Rights ­ Retention by the Seller ­ ITER UT-B Contracts Div March 2007 Page 1 of 5 ex1c-ITER-mar07.doc Exhibit 1C ­ ITER Ref: DEAR 952.227-11 PATENT RIGHTS - RETENTION BY THE SELLER is or may be patentable or otherwise protectable under title 35 of the United States Code, or any novel

Pennycook, Steve

311

DCLL TBM Safety Assessment A key objective for ITER includes integrated testing of blanket concepts suitable for demonstrating fusion  

E-Print Network [OSTI]

prototypical blanket modules into designated ports. Because ITER will be a licensed nuclear facility, occupation radiation exposure (ORE) analyzed, and decommissioning and waste disposal analysis performed

312

ITER vacuum vessel fabrication plan and cost study (D 68) for the international thermonuclear experimental reactor  

SciTech Connect (OSTI)

ITER Task No. 8, Vacuum Vessel Fabrication Plan and Cost Study (D68), was initiated to assess ITER vacuum vessel fabrication, assembly, and cost. The industrial team of Raytheon Engineers & Constructors and Chicago Bridge & Iron (Raytheon/CB&I) reviewed the current vessel basis and prepared a manufacturing plan, assembly plan, and cost estimate commensurate with the present design. The guidance for the Raytheon/CB&I assessment activities was prepared by the ITER Garching Work Site. This guidance provided in the form of work descriptions, sketches, drawings, and costing guidelines for each of the presently identified vacuum vessel Work Breakdown Structure (WBS) elements was compiled in ITER Garching Joint Work Site Memo (Draft No. 9 - G 15 MD 01 94-17-05 W 1). A copy of this document is provided as Appendix 1 to this report. Additional information and clarifications required for the Raytheon/CB&I assessments were coordinated through the US Home Team (USHT) and its technical representative. Design details considered essential to the Task 8 assessments but not available from the ITER Joint Central Team (JCT) were generated by Raytheon/CB&I and documented accordingly.

NONE

1995-01-01T23:59:59.000Z

313

Status of the 1 MeV Accelerator Design for ITER NBI  

SciTech Connect (OSTI)

The beam source of neutral beam heating/current drive system for ITER is needed to accelerate the negative ion beam of 40A with D{sup -} at 1 MeV for 3600 sec. In order to realize the beam source, design and R and D works are being developed in many institutions under the coordination of ITER organization. The development of the key issues of the ion source including source plasma uniformity, suppression of co-extracted electron in D beam operation and also after the long beam duration time of over a few 100 sec, is progressed mainly in IPP with the facilities of BATMAN, MANITU and RADI. In the near future, ELISE, that will be tested the half size of the ITER ion source, will start the operation in 2011, and then SPIDER, which demonstrates negative ion production and extraction with the same size and same structure as the ITER ion source, will start the operation in 2014 as part of the NBTF. The development of the accelerator is progressed mainly in JAEA with the MeV test facility, and also the computer simulation of beam optics also developed in JAEA, CEA and RFX. The full ITER heating and current drive beam performance will be demonstrated in MITICA, which will start operation in 2016 as part of the NBTF.

Kuriyama, M.; Boilson, D.; Hemsworth, R.; Svensson, L.; Graceffa, J.; Schunke, B.; Decamps, H.; Tanaka, M. [ITER Organization, 13067 Saint-Paul-lez-Durance Cede (France); Bonicelli, T.; Masiello, A. [Fusion for Energy, C/Josep Pla 2, 08019 Barcelona (Spain); Bigi, M.; Chitarin, G.; Luchetta, A.; Marcuzzi, D.; Pasqualotto, R.; Pomaro, N.; Serianni, G.; Sonato, P.; Toigo, V.; Zaccaria, P. [Consorzio RFX. Corso Stati Uniti 4 35127 Padova (Italy)

2011-09-26T23:59:59.000Z

314

Experimental Results with the New ITER-like 1 MV SINGAP Accelerator  

SciTech Connect (OSTI)

A new 'ITER-like' accelerator, which is a scaled down version of the ITER SINGAP (SINgle GAP, SINGle APerture) accelerator, has been built and installed on the Cadarache 1 MV test bed. The objective is to demonstrate reliable D- beam acceleration as close as possible to 1 MeV with a current density j- {approx_equal} 200 A/m2 with the beam optics required for ITER, i.e. a beamlet divergence of {<=}7 mrad and beamlet steering within {+-}2 mrad of that specified. High voltage hold off tests have been performed and 940 kV has been held without breakdowns. The first beams up to 850 keV (D-, 15 A/m2) have been obtained after 4 weeks of experiments and the highest current density that has been obtained so far is 85 A/m2 (D-, 580 keV)

Svensson, L.; Esch, H.P.L. de; Hemsworth, R.S.; Massmann, P. [Association EURATOM-CEA, CEA/DSM/DRFC, CEA -Cadarache, 13108 St Paul-lez-Durance (France); Boilson, D. [Association EURATOM-DCU, PRL/NCPST, Glasnevin, Dublin 13 (Ireland)

2005-04-06T23:59:59.000Z

315

Tungsten spectroscopy relevant to the diagnostics development of ITER divertor plasmas  

SciTech Connect (OSTI)

The ITER tokamak will have tungsten divertor tiles and, consequently, the divertor plasmas are expected to contain tungsten ions. The spectral emission from these ions can serve to diagnose the divertor for plasma parameters such as tungsten concentrations, densities, ion and electron temperatures, and flow velocities. The ITER divertor plasmas will likely have densities around 10{sup 14-15} cm{sup -3} and temperatures below 150 eV. These conditions are similar to the plasmas at the Sustained Spheromak Physics Experiment (SSPX) in Livermore. To simulate ITER divertor plasmas, a tungsten impurity was introduced into the SSPX spheromak by prefilling it with tungsten hexacarbonyl prior to the usual hydrogen gas injection and initiation of the plasma discharge. The possibility of using the emission from low charge state tungsten ions to diagnose tokamak divertor plasmas has been investigated using a high-resolution extreme ultraviolet spectrometer.

Clementson, J; Beiersdorfer, P; Magee, E W; McLean, H S; Wood, R D

2009-12-01T23:59:59.000Z

316

TRANSP Tests Of TGLF and Predictions For ITER  

SciTech Connect (OSTI)

Gyro kinetic simulations of turbulence capture some of the features observed in transport, fluctuations, and correlations measured in tokamak plasmas. These codes calculations are CPU intensive, and are not practical for incorporation in present time-dependant transport codes, so reduced models based on these gyro kinetic codes are being used. An example is the TGLF model [1] which is a quasilinear gyrofluid model calibrated to nonlinear results from the GYRO code [2]. Recently TGLF has been incorporated into TRANSP [3].

Robert V Budny, et al

2013-06-02T23:59:59.000Z

317

Quantum mechanical Hamiltonian models of discrete processes that erase their own histories: application to Turing machines  

SciTech Connect (OSTI)

Work done before on the construction of quantum mechanical Hamiltonian models of Turing machines and general descrete processes is extended here to include processes which erase their own histories. The models consist of three phases, the forward process phase in which a map T is iterated and a history of iterations is generated, a copy phase which is activated if and only if T reaches a fix point, and an erase phase which erases the iteration history, undoes the iterations of T and recovers the initial state except for the copy system. A ballast system is used to stop the evolution at the desired state. The general model so constructed is applied to Turing machines. The main changes are that the system undergoing the evolution corresponding to T iterations becomes three systems corresponding to the internal machine, the computation tape, and computation head. Also the copy phase becomes more complex since it is desired that this correspond also to a copying Turing machine.

Benioff, P.A.

1981-01-01T23:59:59.000Z

318

Cyber Incidents Involving Control Systems  

SciTech Connect (OSTI)

The Analysis Function of the US-CERT Control Systems Security Center (CSSC) at the Idaho National Laboratory (INL) has prepared this report to document cyber security incidents for use by the CSSC. The description and analysis of incidents reported herein support three CSSC tasks: establishing a business case; increasing security awareness and private and corporate participation related to enhanced cyber security of control systems; and providing informational material to support model development and prioritize activities for CSSC. The stated mission of CSSC is to reduce vulnerability of critical infrastructure to cyber attack on control systems. As stated in the Incident Management Tool Requirements (August 2005) ''Vulnerability reduction is promoted by risk analysis that tracks actual risk, emphasizes high risk, determines risk reduction as a function of countermeasures, tracks increase of risk due to external influence, and measures success of the vulnerability reduction program''. Process control and Supervisory Control and Data Acquisition (SCADA) systems, with their reliance on proprietary networks and hardware, have long been considered immune to the network attacks that have wreaked so much havoc on corporate information systems. New research indicates this confidence is misplaced--the move to open standards such as Ethernet, Transmission Control Protocol/Internet Protocol, and Web technologies is allowing hackers to take advantage of the control industry's unawareness. Much of the available information about cyber incidents represents a characterization as opposed to an analysis of events. The lack of good analyses reflects an overall weakness in reporting requirements as well as the fact that to date there have been very few serious cyber attacks on control systems. Most companies prefer not to share cyber attack incident data because of potential financial repercussions. Uniform reporting requirements will do much to make this information available to Department of Homeland Security (DHS) and others who require it. This report summarizes the rise in frequency of cyber attacks, describes the perpetrators, and identifies the means of attack. This type of analysis, when used in conjunction with vulnerability analyses, can be used to support a proactive approach to prevent cyber attacks. CSSC will use this document to evolve a standardized approach to incident reporting and analysis. This document will be updated as needed to record additional event analyses and insights regarding incident reporting. This report represents 120 cyber security incidents documented in a number of sources, including: the British Columbia Institute of Technology (BCIT) Industrial Security Incident Database, the 2003 CSI/FBI Computer Crime and Security Survey, the KEMA, Inc., Database, Lawrence Livermore National Laboratory, the Energy Incident Database, the INL Cyber Incident Database, and other open-source data. The National Memorial Institute for the Prevention of Terrorism (MIPT) database was also interrogated but, interestingly, failed to yield any cyber attack incidents. The results of this evaluation indicate that historical evidence provides insight into control system related incidents or failures; however, that the limited available information provides little support to future risk estimates. The documented case history shows that activity has increased significantly since 1988. The majority of incidents come from the Internet by way of opportunistic viruses, Trojans, and worms, but a surprisingly large number are directed acts of sabotage. A substantial number of confirmed, unconfirmed, and potential events that directly or potentially impact control systems worldwide are also identified. Twelve selected cyber incidents are presented at the end of this report as examples of the documented case studies (see Appendix B).

Robert J. Turk

2005-10-01T23:59:59.000Z

319

Electromagnetic Analysis For The Design Of ITER Diagnostic Port Plugs During Plasma Disruptions  

SciTech Connect (OSTI)

ITER diagnostic port plugs perform many functions including structural support of diagnostic systems under high electromagnetic loads while allowing for diagnostic access to plasma. The design of diagnotic equatorial port plugs (EPP) are largely driven by electromagnetic loads and associate response of EPP structure during plasma disruptions and VDEs. This paper summarizes results of transient electromagnetic analysis using Opera 3d in support of the design activities for ITER diagnostic EPP. A complete distribution of disruption loads on the Diagnostic First Walls (DFWs). Diagnostic Shield Modules (DSMs) and the EPP structure, as well as impact on the system design integration due to electrical contact among various EPP structural components are discussed.

Zhai, Y

2014-03-03T23:59:59.000Z

320

Beyond ITER: Neutral beams for a demonstration fusion reactor (DEMO) (invited)  

SciTech Connect (OSTI)

In the development of magnetically confined fusion as an economically sustainable power source, International Tokamak Experimental Reactor (ITER) is currently under construction. Beyond ITER is the demonstration fusion reactor (DEMO) programme in which the physics and engineering aspects of a future fusion power plant will be demonstrated. DEMO will produce net electrical power. The DEMO programme will be outlined and the role of neutral beams for heating and current drive will be described. In particular, the importance of the efficiency of neutral beam systems in terms of injected neutral beam power compared to wallplug power will be discussed. Options for improving this efficiency including advanced neutralisers and energy recovery are discussed.

McAdams, R., E-mail: roy.mcadams@ccfe.ac.uk [EURATOM/CCFE Association, Culham Science Centre, Abingdon, Oxfordshire OX14 3DB (United Kingdom)

2014-02-15T23:59:59.000Z

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Non-destructive qualification tests for ITER cryogenic axial insulating breaks  

SciTech Connect (OSTI)

In the ITER superconducting magnets the dielectric separation between the CICC (Cable-In-Conduit Conductors) and the helium supply pipes is made through the so-called insulating breaks (IB). These devices shall provide the required dielectric insulation at a 30 kV level under different types of stresses and constraints: thermal, mechanical, dielectric and ionizing radiations. As part of the R and D program, the ITER Organization launched contracts with industrial companies aimed at the qualification of the manufacturing techniques. After reviewing the main functional aspects, this paper describes and discusses the protocol established for non-destructive qualification tests of the prototypes.

Kosek, Jacek [Wroclaw University of Technology, Wybrzeze Wyspianskiego 27, 50-370 Wroclaw, Poland and CERN, Geneva 23,CH-1211 (Switzerland); Lopez, Roberto; Tommasini, Davide [CERN, Geneva 23,CH-1211 (Switzerland); Rodriguez-Mateos, Felix [CERN, Geneva 23,CH-1211, Switzerland and ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul lez Durance (France)

2014-01-29T23:59:59.000Z

322

Bounds on the map threshold of iterative decoding systems with erasure noise  

E-Print Network [OSTI]

BOUNDS ON THE MAP THRESHOLD OF ITERATIVE DECODING SYSTEMS WITH ERASURE NOISE A Thesis by CHIA-WEN WANG Submitted to the O ce of Graduate Studies of Texas A&M University in partial ful llment of the requirements for the degree of MASTER OF SCIENCE... August 2008 Major Subject: Electrical Engineering BOUNDS ON THE MAP THRESHOLD OF ITERATIVE DECODING SYSTEMS WITH ERASURE NOISE A Thesis by CHIA-WEN WANG Submitted to the O ce of Graduate Studies of Texas A&M University in partial ful llment...

Wang, Chia-Wen

2008-10-10T23:59:59.000Z

323

Safety-factor profile tailoring by improved electron cyclotron system for sawtooth control and reverse shear scenarios in ITER  

SciTech Connect (OSTI)

The effect of the predicted local electron cyclotron current driven by the optimized electron cyclotron system on ITER is discussed. A design variant was recently proposed to enlarge the physics program covered by the upper and equatorial launchers. By extending the functionality range of the upper launcher, significant control capabilities of the sawtooth period can be obtained. The upper launcher improvement still allows enough margin to exceed the requirements for neoclassical tearing mode stabilization, for which it was originally designed. The analysis of the sawtooth control is carried on with the ASTRA transport code, coupled with the threshold model by Por-celli, to study the control capabilities of the improved upper launcher on the sawtooth instability. The simulations take into account the significant stabilizing effect of the fusion alpha particles. The sawtooth period can be increased by a factor of 1.5 with co-ECCD outside the q = 1 surface, and decreased by at least 30% with co-ECCD inside q = 1. The present ITER base-line design has the electron cyclotron launchers providing only co-ECCD. The variant for the equatorial launcher proposes the possibility to drive counter-ECCD with 1 of the 3 rows of mirrors: the counter-ECCD can then be balanced with co-ECCD and provide pure ECH with no net driven current. The difference between full co-ECCD off-axis using all 20MW from the equatorial launcher and 20MW co-ECCD driven by 2/3 from the equatorial launcher and 1/3 from the upper launcher is shown to be negligible. Cnt-ECCD also offers greater control of the plasma current density, therefore this analysis addresses the performance of the equatorial launcher to control the central q profile. The equatorial launcher is shown to control very efficiently the value of q{sub 0.2}-q{sub min} in advanced scenarios, if one row provides counter-ECCD.

Zucca, C.; Sauter, O.; Fable, E. [Ecole Polytechnique Federate de Lausanne, Centre de Recherches en Physique des Plasmas, Association EURATOM-Confederation Suisse, CH-1015 Lausanne (Switzerland); Henderson, M. A.; Polevoi, A. [ITER Organization, CHD Dpt, CEN Cadarache 519/007, 13108 Saint-Paul-les-Durance (France); Farina, D.; Ramponi, G. [Istituto di Fisica del Plasma, EURATOM-Enea-CNR Association, Milano (Italy); Saibene, G. [Fusion for Energy, c/Josep Pla, 08019 Barcelona (Spain); Zohm, H. [Max Planck Institut fuer Plasmaphysik IPP-EURATOM Association, Garching (Germany)

2008-11-01T23:59:59.000Z

324

The effect of axial strain cycling on the critical current density and n-value of ITER niobium-tin  

E-Print Network [OSTI]

The effect of axial strain cycling on the critical current density and n-value of ITER niobium-tin niobium-tin VAC and EM-LMI strands and the detailed characterisation of the EM-LMI-TFMC strand at -0 current density and n-value of two ITER candidate niobium-tin strands (EM- LMI and VAC). The strands were

Hampshire, Damian

325

IEEE TRANSACTIONS ON AUDIO, SPEECH, AND LANGUAGE PROCESSING, VOL. 20, NO. 6, AUGUST 2012 1869 Constrained Iterative Speech Enhancement  

E-Print Network [OSTI]

Constrained Iterative Speech Enhancement Using Phonetic Classes Amit Das, Student Member, IEEE, and John H. L enhancement algorithms like Auto-LSP, log-minimum mean squared error (log-MMSE), and log-MMSE with speech--Auditory masked threshold, Auto-LSP, con- strained iterative speech enhancement. I. INTRODUCTION NOISE is present

Texas at Dallas, University of

326

DEVELOPMENT STATUS OF A SiC-FOAM BASED FLOW CHANNEL INSERT FOR A U.S.-ITER DCLL TBM  

E-Print Network [OSTI]

, CA, 91331, U.S.A. The U.S.-ITER DCLL (Dual Coolant Liquid Lead) TBM (Test Blanket Module) uses a Flow structure. I. INTRODUCTION The U.S. ITER Double Coolant Lead Lithium (DCLL) Test Blanket Module (TBM liquid breeder (PbLi) at elevated temperatures of more than 700 o C and at low velocities of ~10 cm

Ghoniem, Nasr M.

327

5506 IEEE TRANSACTIONS ON SIGNAL PROCESSING, VOL. 55, NO. 11, NOVEMBER 2007 On the New Stopping Criteria of Iterative Turbo  

E-Print Network [OSTI]

Criteria of Iterative Turbo Decoding by Using Decoding Threshold Fan-Min Li and An-Yeu (Andy) Wu, Member--Decoding threshold, early termination (ET), extrinsic information transform (EXIT) chart, iterative decoding, turbo codes, turbo principle. I. INTRODUCTION IN 1993, a new class of forward-error-correction (FEC) code

Hung, Shih-Hao

328

Studies involving low protein broiler diets  

E-Print Network [OSTI]

STUDIES INVOLVING L(% PROTEIN BROILER DIETS A Thesis by David Palmer Parkin Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE May 1971 Major Subject...: Poultry Science STUDIES INVOLVING LS& PROTEIN BROILER DIETS A Thesis by David Palmer Parkin Approved as to style and content by: (Chairman of Commit e) ead of. Departmen Me er) (Member) (Memb ) May 1971 ABSTRACT Studies Involving Low Protein...

Parkin, David Palmer

1971-01-01T23:59:59.000Z

329

The Japan Times Printer Friendly Articles France has won the competition to host the International Thermonuclear Experimental Reactor (ITER), the world's first nuclear-  

E-Print Network [OSTI]

the International Thermonuclear Experimental Reactor (ITER), the world's first nuclear- fusion reactor. Japan fought wins by withdrawing ITER bid Thermonuclear fusion utilizes the same process that powers the sun

330

A Comparison of Iterative Methods for Least Squares Support Vector Machine Classi ers  

E-Print Network [OSTI]

and Krylov methods (conjugate gradient, block-conjugate gra- dient). The latter show the best performance focus on two iter- ative algorithms: the successive overrelaxation method and the conjugate gradient steps, they are outperformed by the Krylov methods (conjugate gradient). Because, as will be shown later

331

Print this article Close This Window EU OKs India joining ITER nuclear reactor project  

E-Print Network [OSTI]

Print this article Close This Window EU OKs India joining ITER nuclear reactor project Fri Dec 2-billion-euro project to build an experimental nuclear fusion reactor that in the long-run could provide virtually unlimited, cheap and clean energy. The EU's willingness to work with India on a civil nuclear

332

Templates for the Solution of Linear Systems: Building Blocks for Iterative Methods 1  

E-Print Network [OSTI]

Templates for the Solution of Linear Systems: Building Blocks for Iterative Methods 1 Richard of the Office of Energy Research, U.S. Department of Energy, under Contract DE­AC05­84OR21400, and the Stichting This book is also available in Postscript from over the Internet. To retrieve the postscript file you can

Mignotte, Max

333

AN ITERATIVE ROUTE CONSTRUCTION AND IMPROVEMENT ALGORITHM FOR THE VEHICLE ROUTING PROBLEM WITH SOFT  

E-Print Network [OSTI]

time windows exceeds the number of available vehicles, (b) a study of cost-service tradeoffs of available vehicles, (b) a study of cost-service tradeoffs is required, and (c) the dispatcher has1 AN ITERATIVE ROUTE CONSTRUCTION AND IMPROVEMENT ALGORITHM FOR THE VEHICLE ROUTING PROBLEM

Bertini, Robert L.

334

ITER-like wall sliced beryllium tiles The JET Enhanced Performance 2 (EP2) shutdown  

E-Print Network [OSTI]

ITER-like wall sliced beryllium tiles Background The JET Enhanced Performance 2 (EP2) shutdown and remote handling equipment. JET remote handling systems #12;Outcome The EP2 shutdown was successful of the remote handling system are compatible with the required component manipulation. Pre EP2 shutdown Mid

335

Improved Confinement in JET High {beta} Plasmas with an ITER-Like Wall  

E-Print Network [OSTI]

The replacement of the JET carbon wall (C-wall) by a Be/W ITER-like wall (ILW) has affected the plasma energy confinement. To investigate this, experiments have been performed with both the C-wall and ILW to vary the heating power over a wide range for plasmas with different shapes.

Challis, C D; Beurskens, M; Buratti, P; Delabie, E; Drewelow, P; Frassinetti, L; Giroud, C; Hawkes, N; Hobirk, J; Joffrin, E; Keeling, D; King, D B; Maggi, C F; Mailloux, J; Marchetto, C; McDonald, D; Nunes, I; Pucella, G; Saarelma, S; Simpson, J

2015-01-01T23:59:59.000Z

336

ITER Export Control Awareness Information UT-B Contracts Div. Page 1 of 8  

E-Print Network [OSTI]

to manage and implement identified work elements within the ITER Fusion facility to be built in Cadarache with the Department of Energy and/or Nuclear Regulatory Commission. It should be noted that the design information.pdf #12;Commodity Classification Request Work Item Reference Number ITR1007 Status: ACCEPTED Print

Pennycook, Steve

337

MIMO PID Tuning via Iterated LMI Restriction S. Boyd M. Hast K. J. Astrom  

E-Print Network [OSTI]

MIMO PID Tuning via Iterated LMI Restriction S. Boyd M. Hast K. J. °Astr¨om July 2, 2014 Abstract We formulate multi-input multi-output (MIMO) proportional-integral-derivative (PID) controller design, and provides a simple automated method for tuning MIMO PID controllers. The method is readily extended in many

338

PPPL3246 Preprint: April 1997, UC420 THE PHYSICS ROLE OF ITER  

E-Print Network [OSTI]

Plasma Physics Laboratory ABSTRACT Experimental research on the International Thermonuclear Experimental­called ``disruptions'', in regimes of high plasma current and thermal energy; and (iii) physics of a ``radiative issues in the physics of reactor­like plasmas. First and foremost, experiments in ITER will explore

339

PPPL-3246 -Preprint: April 1997, UC-420 THE PHYSICS ROLE OF ITER  

E-Print Network [OSTI]

Plasma Physics Laboratory ABSTRACT Experimental research on the International Thermonuclear Experimental issues in the physics of reactor-like plasmas. First and foremost, experiments in ITER will explore the physics issues of "burning plasmas" -- plasmas that are dominantly self-heated by alpha-particles created

340

Paradigm Changes in High Temperature Plasma Physics Research and Implications for ITER  

SciTech Connect (OSTI)

Significant high temperature plasma research in both the magnetic and inertial confinement regimes led to the official launching of the International Thermonuclear Experimental Reactor (ITER) project which is aimed at challenging controlled fusion power for human kind. In particular, such an endeavor originated from the fruitful research outcomes from the world wide magnetic confinement devices (primarily based on the Tokamak approach) mainly in advanced countries (US, EU, and Japan). In recent years, all new steady state capable Tokamak devices are operated and/or constructed in Asian countries and incidentally, the majority of the ITER consortium consists of Asian countries. This provides an opportunity to revisit the unresolved essential physics issues and/or extend the understanding of the transient physics to the required steady state operation so that ITER can benefit from these efforts. The core physics of a magnetically confined hot plasma has two essential components; plasma stability and cross-field energy transport physics. Complete understanding of these two areas is critical for the successful operation of ITER and perhaps, Demo reactor construction. In order to have stable high beta plasmas with a sufficiently long confinement time, the physics of an abrupt disruption and sudden deterioration of the energy transport must be understood and conquered. Physics issues associated with transient harmful MHD behavior and turbulence based energy transport are extremely complicated and theoretical understanding needs a clear validation and verification with a new research approach such as a multi-dimensional visualization.

Hyeon K. Park

2008-02-22T23:59:59.000Z

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Europe and Japan with the elbow-with-elbow to accomodate engine ITER  

E-Print Network [OSTI]

.12.03|13h1713h17 ? The competition for the machine installation of with thermonuclear fusion is announced, selected after a survey campaign, where the experimental engine with thermonuclear fusion ITER experts - thermonuclear fusion, who come to supra establish a new record in the engine with Tore fusion

342

Non-iterative joint decoding and signal processing: universal coding approach for channels with memory  

E-Print Network [OSTI]

in an error free manner through the use of a capacity achieving code for a memoryless channel. Computational complexity of the proposed receiver structure is less than that of one iteration of the turbo receiver. We also provide the proof showing...

Nangare, Nitin Ashok

2006-08-16T23:59:59.000Z

343

NATURE | Q&A Five-year delay would spell end of ITER  

E-Print Network [OSTI]

States has high scientific and technological capability in fusion energy and has been one of the leading on Earth has long been a dream for physicists. In 2006, a team from the European Union, China, India, Japan of weight-loss Elizabeth Gibney Print #12;Related stories ITER keeps eye on prize Japan quake rocks fusion

344

AN ITERATIVE SPATIO-TEMPORAL SPEECH ENHANCEMENT ALGORITHM FOR MICROPHONE ARRAYS  

E-Print Network [OSTI]

AN ITERATIVE SPATIO-TEMPORAL SPEECH ENHANCEMENT ALGORITHM FOR MICROPHONE ARRAYS !"#"$ %&'t" "nd +c ABSTRACT We present a new spatio-temporal algorithm for speech enhancement using microphone arrays. Our-dependent parameter settings. Index Terms4 Speech enhancement, acoustic arrays, adaptive arrays, eigenvalues

Douglas, Scott C.

345

Disruption mitigation for ITER Disruptions are sudden unplanned terminations of the plasma that can  

E-Print Network [OSTI]

damage the plasma chamber from thermal loads, high magnetic forces, and runaway electrons. A reliable fast acting tool to mitigate these effects in ITER burning plasmas by the injection of large quantities be located inside a port plug for close proximity to the plasma and fast injection. Multiple injectors can

346

Fuel Source Isotopic Tailoring Impact on ITER Design, Operation and Safety  

E-Print Network [OSTI]

1 Fuel Source Isotopic Tailoring and Its Impact on ITER Design, Operation and Safety M. J. Gouge, W. The isotopic tailoring concept consists of utilizing a tritium-rich pellet source for core fueling and a deuterium- rich gas source for edge fueling. Because of the improved particle confinement associated

347

Solution characters of iterative coupling between energy simulation and CFD programs  

E-Print Network [OSTI]

third of the primary energy consumption and two thirds of the electricity. Designing an energy/heating loads, coil loads, and energy consumption can be obtained on an hourly or sub-hourly basis for a period1 Solution characters of iterative coupling between energy simulation and CFD programs Zhiqiang

Chen, Qingyan "Yan"

348

Iteration Space Tiling for Distributed Memory Machines J. Ramanujam y and P. Sadayappan z  

E-Print Network [OSTI]

levels of flexibility, scalability and performance but programming these machines remains a difficultIteration Space Tiling for Distributed Memory Machines J. Ramanujam y and P. Sadayappan z y Department of Electrical and Computer Engineering, Louisiana State University, Baton Rouge, LA 70803

Ramanujam, J. "Ram"

349

On the Logic of Iterated Belief Revision Adnan Darwiche and Judea Pearl  

E-Print Network [OSTI]

and inadequacies of the operator--based approach to belief revision [3, 4, 5, 13]. This paper addresses oneOn the Logic of Iterated Belief Revision Adnan Darwiche and Judea Pearl Cognitive Systems preservation of conditional beliefs during belief revision, thus permitting improper responses to sequences

California at Los Angeles, University of

350

Fabrication of the First US ITER TF Conductor Sample for Qualification in SULTAN Facility  

E-Print Network [OSTI]

A pair of 3.5 m long ITER TF size straight conductors has been fabricated into a conductor short sample and submitted to the SULTAN facility at CRPP for cold test. The sample used a triplet-based cabling pattern in one leg ...

Miller, John R.

351

Analysis of a Classification-based Policy Iteration Algorithm Alessandro Lazaric alessandro.lazaric@inria.fr  

E-Print Network [OSTI]

be solved exactly and approximation techniques are required. In approximate policy iteration (API issues, mainly 3 and 4,1 variants of API have been proposed that replace the usual value function label. In this case, (x, a) for the rest of the actions are labeled negative and added to the training

352

EXPERIMENTALSTUDY OF THE EFFECTIVETHERMAL CONDUCTIVITYOFA PACKED BED AS A TEMPERATURECONTROL MECHANISMFOR ITER CERAMICBREEDERBLANKETDESIGNS *  

E-Print Network [OSTI]

to maximize reli- ability. A novel and practical concept was proposed for the thermal resistance gap between were used as alternate low thermal conductivity gases. With this set of materials, a good range the coolant and solid breeder to allow their operating temperatures to be optimized for ITER.[11 This thermal

Raffray, A. René

353

Generics, habituals, and iteratives Sentences may express information about particular events, such as  

E-Print Network [OSTI]

cough or flap (a wing)'. In English, John coughed can be understood as saying that he coughed once implications, especially those of intensity and/or prolongation. In English, John coughed and coughed is iterative in interpretation, like one understanding of the simple John coughed, but in addition implies

Makous, Walter

354

Thirty states sign ITER nuclear fusion plant deal 1 hour, 28 minutes ago  

E-Print Network [OSTI]

Thirty states sign ITER nuclear fusion plant deal 1 hour, 28 minutes ago Representatives of more than 30 countries signed a deal on Tuesday to build the world's most advanced nuclear fusion reactor nuclear reactors, but critics argue it could be at least 50 years before a commercially viable reactor

355

Fusion Engineering and Design 42 (1998) 235245 Verification of ITER shielding capability and FENDL data  

E-Print Network [OSTI]

of the calculated-to-experimental (C/E) data. These two objectives will guide designers with regard and calculated data that should be implemented in the design process. Both differential and integral experimentalFusion Engineering and Design 42 (1998) 235­245 Verification of ITER shielding capability and FENDL

Abdou, Mohamed

356

U.S. PLANS AND STRATEGY FOR ITER BLANKET TESTING , M. Sawan4  

E-Print Network [OSTI]

U.S. PLANS AND STRATEGY FOR ITER BLANKET TESTING M. Abdou1 , D. Sze2 , C. Wong3 , M. Sawan4 , A. Ying1 , N. B. Morley1 , S. Malang5 1 UCLA Fusion Engineering Sciences, Los Angeles, CA, abdou

Abdou, Mohamed

357

Test Strategy for the European HCPB Test Blanket Module in ITER  

SciTech Connect (OSTI)

According to the European Blanket Programme two blanket concepts, the Helium Cooled Pebble Bed (HCPB) and a Helium Cooled Lithium Lead (HCLL) will be tested in ITER. During 2004 the test blanket modules (TBM) of both concepts were redesigned with the goal to use as much as possible similar design options and fabrication techniques for both types in order to reduce the European effort for TBM development. The result is a robust TBM box being able to withstand 8 MPa internal pressure in case of in-box LOCA; the TBM box consists of First wall (FW), caps, stiffening grid and manifolds. The box is filled with typically 18 and 24 breeding units (BU), for HCPB and HCLL respectively. A breeding unit has about 200 mm in poloidal and toroidal direction and about 400 mm in radial direction; the design is adapted to contain and cooling ceramic breeder/beryllium pebble beds for the HCPB and eutectic Lithium-Lead for the HCLL.The use of a new material, EUROFER, and the innovative design of these Helium Cooled components call for a large qualification programme before the installation in ITER; availability and safety of ITER should not be jeopardised by a failure of these components. Fabrication technologies especially in the welding processes (diffusion welding, EB, TIG, LASER) need to be tested in the manufacturing of large mock-ups; an extensive out-of-pile programme in Helium facility should be foreseen for the verification of the concept from basic helium cooling functions (uniformity of flow in parallel channels, heat transfer coefficient in FW, etc.) up to the verification of large portions of the TBM design under relevant ITER loading.In ITER the TBM will have the main objective to collect information that will contribute to the final design of DEMO blankets. A strategy has been proposed in 2001 that leads to the tests in ITER 4 different Test Blanket Modules (TBM's) type during the first 10 years of ITER operation. For the new HCPB design this strategy is confirmed with some additional possibilities taking into account the modular design of the breeding zone.

Boccaccini, L.V.; Meyder, R.; Fischer, U. [Forschungszentrum Karlsruhe (Germany)

2005-05-15T23:59:59.000Z

358

Slide 1/14Fusion Power Associate Washington DC 10-11 December 2013OM13897 Status Report of the ITER Project  

E-Print Network [OSTI]

as an independent international organization ­ Develop a process where objectives and strategy defined by the DG-General of the ITER Organization Aerial view of ITER Site in September 2013 (F4E) #12;Slide 2/14Fusion Power Associate more power than it receives; · The ITER Project creates a new collaborative culture and standard

359

24th IAEA Fusion Energy Conference, San Diego, CA, October 8-13, 2012 Slide 1 The ITER Blanket System Design  

E-Print Network [OSTI]

24th IAEA Fusion Energy Conference, San Diego, CA, October 8-13, 2012 Slide 1 The ITER Blanket-13, 2012 Slide 2 Blanket Effort Conducted within BIPT Blanket Integrated Product Team ITER-13, 2012 Slide 3 Blanket System Functions Main functions of ITER Blanket System: · Exhaust the majority

Raffray, A. René

360

Revisiting Stopping Rules for Iterative Methods used in Emission Tomography  

E-Print Network [OSTI]

Recon, Inc., 60 Hazelwood Dr., Champaign, IL 61820, USA b Arizona State University, School of Mathematical, [2], and yields the maximum likelihood (ML) model with the expec- tation maximization (EM) algorithm subsets EM, (OSEM) [3, 4], has been adopted by a number of manufacturers [5]. Still many important issues

Renaut, Rosemary

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
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361

Compact, Convex Upper Bound Iteration for Approximate POMDP Planning  

E-Print Network [OSTI]

uncertainty How to act based on past experience Maximize long term reward Wide range of applications Robotics and autonomous agent design Helicopter control, Robot navigation and mapping Nursing , Elderly assistance Others #12;POMDP model s0 s0 a1 a1 o1 o1 s1 s1 s2 s2 a2 a2 o2 o2 st st at at ot ot r0 r0 r1 r1 r2 r2 rt rt

Wang, Tao

362

Factors Involved in Search Dog Training  

E-Print Network [OSTI]

involved in training competent search dogs. Obedience training methods, age training was initiated, previous handler canine training experience, and handler perception and emotional attachment to their search dog were examined through a sixty-six question...

Alexander, Michael B.

2010-07-14T23:59:59.000Z

363

Comparisons of Predicted Plasma Performance in ITER H-mode Plasmas with Various Mixes of External He  

SciTech Connect (OSTI)

Performance in H-mode DT plasmas in ITER with various choices of heating systems are predicted and compared. Combinations of external heating by Negative Ion Neutral Beam Injection (NNBI), Ion Cyclotron Range of Frequencies (ICRF), and Electron Cyclotron Heating (ECH) are assumed. Scans with a range of physics assumptions about boundary temperatures in the edge pedestal, alpha ash transport, and toroidal momentum transport are used to indicate effects of uncertainties. Time-dependent integrated modeling with the PTRANSP code is used to predict profiles of heating, beam torque, and plasma profiles. The GLF23 model is used to predict temperature profiles. Either GLF23 or the assumption of a constant ratio for ?ø/?i is used to predict toroidal rotation profiles driven by the beam torques. Large differences for the core temperatures are predicted with different mixes of the external heating during the density and current ramp-up phase, but the profiles are similar during the flattop phase. With ?ø/?i = 0.5, the predicted toroidal rotation is relatively slow and the flow shear implied by the pressure, toroidal rotation, and neoclassical poloidal rotation are not sufficient to cause significant changes in the energy transport or steady state temperature profiles. The GLF23-predicted toroidal rotation is faster by a factor of six, and significant flow shear effects are predicted.

R.V. Budny

2009-03-20T23:59:59.000Z

364

Ion cyclotron resonance frequency heating in JET during initial operations with the ITER-like wall  

SciTech Connect (OSTI)

In 2011/12, JET started operation with its new ITER-Like Wall (ILW) made of a tungsten (W) divertor and a beryllium (Be) main chamber wall. The impact of the new wall materials on the JET Ion Cyclotron Resonance Frequency (ICRF) operation is assessed and some important properties of JET plasmas heated with ICRF are highlighted. A???20% reduction of the antenna coupling resistance is observed with the ILW as compared with the JET carbon (JET-C) wall. Heat-fluxes on the protecting limiters close the antennas, quantified using Infra-Red thermography (maximum 4.5?MW/m{sup 2} in current drive phasing), are within the wall power load handling capabilities. A simple RF sheath rectification model using the antenna near-fields calculated with the TOPICA code can reproduce the heat-flux pattern around the antennas. ICRF heating results in larger tungsten and nickel (Ni) contents in the plasma and in a larger core radiation when compared to Neutral Beam Injection (NBI) heating. The location of the tungsten ICRF specific source could not be identified but some experimental observations indicate that main-chamber W components could be an important impurity source: for example, the divertor W influx deduced from spectroscopy is comparable when using RF or NBI at same power and comparable divertor conditions, and Be evaporation in the main chamber results in a strong reduction of the impurity level. In L-mode plasmas, the ICRF specific high-Z impurity content decreased when operating at higher plasma density and when increasing the hydrogen concentration from 5% to 15%. Despite the higher plasma bulk radiation, ICRF exhibited overall good plasma heating performance; the power is typically deposited at the plasma centre while the radiation is mainly from the outer part of the plasma bulk. Application of ICRF heating in H-mode plasmas has started, and the beneficial effect of ICRF central electron heating to prevent W accumulation in the plasma core has been observed.

Jacquet, P., E-mail: philippe.jacquet@ccfe.ac.uk; Monakhov, I.; Arnoux, G.; Brix, M.; Graham, M.; Meigs, A.; Sirinelli, A. [Euratom/CCFE Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Bobkov, V.; Devaux, S.; Drewelow, P.; Pütterich, T. [Max-Planck-Institut für Plasmaphysik, EURATOM-Assoziation, Garching (Germany); Colas, L. [CEA, IRFM, F-13108 Saint-Paul-Lez-Durance (France); Czarnecka, A. [Association Euratom-IPPLM, Hery 23, 01-497 Warsaw (Poland); Lerche, E.; Van-Eester, D. [Association EURATOM-Belgian State, ERM-KMS, Brussels (Belgium); Mayoral, M.-L. [Euratom/CCFE Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); EFDA Close Support Unit, Garching (Germany); Brezinsek, S. [IEK-4, Forschungszentrum Jülich, Association EURATOM-FZJ, Jülich (Germany); Campergue, A.-L. [Ecole Nationale des Ponts et Chaussées, F77455 Marne-la-Vallée (France); Klepper, C. C. [Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-6169 (United States); Milanesio, D. [Politecnico di Torino, Department of Electronics, Torino (Italy); and others

2014-06-15T23:59:59.000Z

365

arXiv:hep-ex/0211027v111Nov2002 Search for neutrinoless decays involving the K0  

E-Print Network [OSTI]

arXiv:hep-ex/0211027v111Nov2002 1 Search for neutrinoless decays involving the K0 S meson K neutrinoless LFV modes within a model involving heavy Dirac neutrinos. The branching fractions depend

366

Hybrid preconditioning for iterative diagonalization of ill-conditioned generalized eigenvalue problems in electronic structure calculations  

SciTech Connect (OSTI)

The iterative diagonalization of a sequence of large ill-conditioned generalized eigenvalue problems is a computational bottleneck in quantum mechanical methods employing a nonorthogonal basis for ab initio electronic structure calculations. We propose a hybrid preconditioning scheme to effectively combine global and locally accelerated preconditioners for rapid iterative diagonalization of such eigenvalue problems. In partition-of-unity finite-element (PUFE) pseudopotential density-functional calculations, employing a nonorthogonal basis, we show that the hybrid preconditioned block steepest descent method is a cost-effective eigensolver, outperforming current state-of-the-art global preconditioning schemes, and comparably efficient for the ill-conditioned generalized eigenvalue problems produced by PUFE as the locally optimal block preconditioned conjugate-gradient method for the well-conditioned standard eigenvalue problems produced by planewave methods.

Cai, Yunfeng, E-mail: yfcai@math.pku.edu.cn [LMAM and School of Mathematical Sciences, Peking University, Beijing 100871 (China) [LMAM and School of Mathematical Sciences, Peking University, Beijing 100871 (China); Department of Computer Science, University of California, Davis 95616 (United States); Bai, Zhaojun, E-mail: bai@cs.ucdavis.edu [Department of Computer Science and Department of Mathematics, University of California, Davis 95616 (United States)] [Department of Computer Science and Department of Mathematics, University of California, Davis 95616 (United States); Pask, John E., E-mail: pask1@llnl.gov [Condensed Matter and Materials Division, Lawrence Livermore National Laboratory, Livermore, CA 94550 (United States); Sukumar, N., E-mail: nsukumar@ucdavis.edu [Department of Civil and Environmental Engineering, University of California, Davis 95616 (United States)

2013-12-15T23:59:59.000Z

367

Assessment of database for interaction of tritium with ITER plasma facing materials  

SciTech Connect (OSTI)

The present work surveys recent literature on hydrogen isotope interactions with Be, SS and Inconels, Cu, C, and V, and alloys of Cu and V. The goals are (1) to provide input to the International Thermonuclear Experimental Reactor (ITER) team to help with tritium source term estimates for the Early Safety and Environmental Characterization Study and (2) to provide guidance for planning additional research that will be needed to fill gaps in the present materials database. Properties of diffusivity, solubility, permeability, chemical reactions, Soret effect, recombination coefficient, surface effects, trapping, porosity, layered structures, interfaces, and oxides are considered. Various materials data are tabulated, and a matrix display shows an assessment of the quality of the data available for each main property of each material. Recommendations are made for interim values of diffusivity and solubility to be used, pending further discussion by the ITER community.

Dolan, T.J.; Anderl, R.A.

1994-09-01T23:59:59.000Z

368

Neutronics and thermal design analyses of US solid breeder blanket for ITER  

SciTech Connect (OSTI)

The US Solid Breeder Blanket is designed to produce the necessary tritium required for the ITER operation and to operate at power reactor conditions as much as possible. Safety, low tritium inventory, reliability, flexibility cost, and minimum R D requirements are the other design criteria. To satisfy these criteria, the produced tritium is recovered continuously during operation and the blanket coolant operates at low pressure. Beryllium multiplier material is used to control the solid-breeder temperature. Neutronics and thermal design analyses were performed in an integrated manner to define the blanket configuration. The reference parameters of ITER including the operating scenarios, the neutron wall loading distribution and the copper stabilizer are included in the design analyses. Several analyses were performed to study the impact of the reactor parameters, blanket dimensions, material characteristics, and heat transfer coefficient at the material interfaces on the blanket performance. The design analyses and the results from the different studies are summarized. 6 refs., 3 figs., 3 tabs.

Gohar, Y.; Billone, M.; Attaya, H. (Argonne National Lab., IL (USA)); Sawan, M. (Wisconsin Univ., Madison, WI (USA))

1990-09-01T23:59:59.000Z

369

US ITER (International Thermonuclear Experimental Reactor) shield and blanket design activities  

SciTech Connect (OSTI)

This paper summarizes nuclear-related work in support of the US effort for the International Thermonuclear Experimental Reactor (ITER) Study. Primary tasks carried out during the past year include design improvements of the inboard shield developed for the TIBER concept, scoping studies of a variety of tritium breeding blanket options, development of necessary design guidelines and evaluation criteria for the blanket options, further safety considerations related to nuclear components, and issues regarding structural materials for an ITER device. The blanket concepts considered are the aqueous/Li salt solution, a water-cooled, solid breeder blanket, a helium-cooled, solid-breeder blanket, a blanket cooled by helium containing lithium-bearing particulates, and a blanket concept based on breeding tritium from He/sup 3/. 1 ref., 2 tabs.

Baker, C.C.

1988-08-01T23:59:59.000Z

370

Review of the International Thermonuclear Experimental Reactor (ITER) detailed design report  

SciTech Connect (OSTI)

Dr. Martha Krebs, Director, Office of Energy Research at the US Department of Energy (DOE), wrote to the Fusion Energy Sciences Advisory Committee (FESAC), in letters dated September 23 and November 6, 1996, requesting that FESAC review the International Thermonuclear Experimental Reactor (ITER) Detailed Design Report (DDR) and provide its view of the adequacy of the DDR as part of the basis for the United States decision to enter negotiations with the other interested Parties regarding the terms and conditions for an agreement for the construction, operations, exploitation and decommissioning of ITER. The letter from Dr. Krebs, referred to as the Charge Letter, provided context for the review and a set of questions of specific interest.

NONE

1997-04-18T23:59:59.000Z

371

The ITER pre-compression rings – A first in cryogenic composite technology  

SciTech Connect (OSTI)

The ITER Pre-Compression Rings represent one of the heaviest composite structures ever manufactured as a single piece and the largest - the outer diameter will be above 5.5 meters - intended for use in a cryogenic environment. With a cross section of 337 mm × 288 mm, each item will weigh more than 3,000 kg. A development program, based on filament wound and dry wound S2 glass unidirectional fibers, the latter processed by VARTM, was completed on one fifth scale rings, and these materials and techniques were shown to be satisfactory. The paper describes how a technology applied to build up primary structures of European launchers is being accommodated to produce the ITER Pre-Compression Rings, fulfilling its extremely challenging requirements. In addition, we will describe how the structural analysis is correlated with the test results of scaled down rings, as well as how the pre-compression rings’ manufacturing process will be qualified.

Rajainmaki, Hannu; Fanthome, John; Losasso, Marcello [Fusion for Energy, C/ Josep Pla, n. 2, E-08019 Barcelona (Spain); Foussat, Arnaud [ITER Organisation, 13108 St. Paul-lez-Durance (France); Rodriguez, Jesus [EADS CASA Espacio S.L., Av. de Aragón 404, E-28022 Madrid (Spain); Evans, David; Diaz, Victor [Advanced Cryogenic Materials Ltd, Abingdon, OX14 2HQ (United Kingdom)

2014-01-27T23:59:59.000Z

372

Experimental neutronics tests for a neutron activation system for the European ITER TBM  

SciTech Connect (OSTI)

We are investigating methods for neutron flux measurement in the ITER TBM. In particular we have tested sets of activation materials leading to induced gamma activities with short half-lives of the order of tens of seconds up to minutes and standard activation materials. Packages of activation foils have been irradiated with the intense neutron generator of Technical University of Dresden in a pure DT neutron field as well as in a neutronics mock-up of the European ITER HCLL TBM. An important aim was to check whether the gamma activity induced in the activation foils in these packages could be measured simultaneously. It was indeed possible to identify gamma lines of interest in gamma-ray measurements immediately after extraction from the irradiation.

Klix, A.; Fischer, U. [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Gehre, D. [Technical University of Dresden, IKTP, Zellescher Weg 19, 01062 Dresden (Germany); Kleizer, G. [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany and Budapest University of Technology and Economics, M?egyetem rkp. 3-9. H-1111 Budapest (Hungary); Raj, P. [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany and Université Paris-Sud, 15 rue Georges Clemenceau, F-91405 Paris (France); Rovni, I. [Budapest University of Technology and Economics, M?egyetem rkp. 3-9. H-1111 Budapest (Hungary); Ruecker, Tom [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany and University of Applied Sciences Zittau-Goerlitz, Theodor-Körner-Allee 16, D-02754 Zittau (Germany)

2014-08-21T23:59:59.000Z

373

In-Vessel Coil Material Failure Rate Estimates for ITER Design Use  

SciTech Connect (OSTI)

The ITER international project design teams are working to produce an engineering design for construction of this large tokamak fusion experiment. One of the design issues is ensuring proper control of the fusion plasma. In-vessel magnet coils may be needed for plasma control, especially the control of edge localized modes (ELMs) and plasma vertical stabilization (VS). These coils will be lifetime components that reside inside the ITER vacuum vessel behind the blanket modules. As such, their reliability is an important design issue since access will be time consuming if any type of repair were necessary. The following chapters give the research results and estimates of failure rates for the coil conductor and jacket materials to be used for the in-vessel coils. Copper and CuCrZr conductors, and stainless steel and Inconel jackets are examined.

L. C. Cadwallader

2013-01-01T23:59:59.000Z

374

Clover Action for Blue Gene-Q and Iterative solvers for DWF  

E-Print Network [OSTI]

In Lattice QCD, a major challenge in simulating physical quarks is the computational complexity of these simulations. In this proceeding, we describe the optimisation of Clover fermion action for Blue gene-Q architecture and how different iterative solvers behave for Domain Wall Fermion action. We find that the optimised Clover term achieved a maximum efficiency of 29.1% and 20.2% for single and double precision respectively for iterative Conjugate Gradient solver. For Domain Wall Fermion action (DWF) we found that Modified Conjugate Residual(MCR) as the most efficient solver compared to CG and GCR. We have developed a new multi-shift MCR algorithm that is 18.5% faster compared to multi-shift CG for the evaluation of rational functions in RHMC.

Karthee Sivalingam; Peter Boyle

2014-08-28T23:59:59.000Z

375

Design and Overview of 100 kV Bushing for the DNB Injector of ITER  

SciTech Connect (OSTI)

The 100 kV bushing is one of the most important and technologically challenging Safety Important Class (SIC) components of the Diagnostic Neutral Beam (DNB) injector of ITER. It forms interface between gas insulated electrical transmission line and torus primary vacuum and acts as a vacuum feedthrough of ITER. Design optimization has been carried out to meet the electric and structural requirements based on its classification. Unlike HNB bushing, single stage bushing is designed to provide 100 kV isolation. Finite Element Analysis (FEA) based optimization has been carried out for electrostatic and structural analysis. Manufacturing assembly sequence is studied and presented in this paper. However validation of the same is foreseen from manufacturer.

Shah, Sejal; Bandyopadhyay, M.; Rotti, C.; Singh, M. J.; Roopesh, G.; Chakraborty, A. K. [ITER-India, Institute for Plasma Research, Gandhinagar-382025, Gujarat (India); Rajesh, S. [ITER-India, Institute for Plasma Research, Gandhinagar-382025, Gujarat (India); Microelectronics and Materials Physics Labs, P.O.Box 4500, FIN-90014 University of Oulu (Finland); Nishad, S.; Srusti, B. [DesignTech Systems Ltd, Banjara Hills, Hyderabad, Andhra Pradesh-500034 (India); Schunke, B.; Hemsworth, R.; Chareyre, J.; Svensson, L. [ITER Organisation, Route de Vinon, CS 90 046, 13067 St. Paul lez Durance Cedex (France)

2011-09-26T23:59:59.000Z

376

Nonlinear Projective-Iteration Methods for Solving Transport Problems on Regular and Unstructured Grids  

SciTech Connect (OSTI)

This is a project in the field of fundamental research on numerical methods for solving the particle transport equation. Numerous practical problems require to use unstructured meshes, for example, detailed nuclear reactor assembly-level calculations, large-scale reactor core calculations, radiative hydrodynamics problems, where the mesh is determined by hydrodynamic processes, and well-logging problems in which the media structure has very complicated geometry. Currently this is an area of very active research in numerical transport theory. main issues in developing numerical methods for solving the transport equation are the accuracy of the numerical solution and effectiveness of iteration procedure. The problem in case of unstructured grids is that it is very difficult to derive an iteration algorithm that will be unconditionally stable.

Dmitriy Y. Anistratov; Adrian Constantinescu; Loren Roberts; William Wieselquist

2007-04-30T23:59:59.000Z

377

Current Control in ITER Steady State Plasmas With Neutral Beam Steering  

SciTech Connect (OSTI)

Predictions of quasi steady state DT plasmas in ITER are generated using the PTRANSP code. The plasma temperatures, densities, boundary shape, and total current (9 - 10 MA) anticipated for ITER steady state plasmas are specified. Current drive by negative ion neutral beam injection, lower-hybrid, and electron cyclotron resonance are calculated. Four modes of operation with different combinations of current drive are studied. For each mode, scans with the NNBI aimed at differing heights in the plasma are performed to study effects of current control on the q profile. The timeevolution of the currents and q are calculated to evaluate long duration transients. Quasi steady state, strongly reversed q profiles are predicted for some beam injection angles if the current drive and bootstrap currents are sufficiently large.

R.V. Budny

2009-09-10T23:59:59.000Z

378

Irradiation tests of ITER candidate Hall sensors using two types of neutron spectra  

SciTech Connect (OSTI)

We report on irradiation tests of InSb based Hall sensors at two irradiation facilities with two distinct types of neutron spectra. One was a fission reactor neutron spectrum with a significant presence of thermal neutrons, while another one was purely fast neutron field. Total neutron fluence of the order of 10{sup 16} cm{sup -2} was accumulated in both cases, leading to significant drop of Hall sensor sensitivity in case of fission reactor spectrum, while stable performance was observed at purely fast neutron spectrum. This finding suggests that performance of this particular type of Hall sensors is governed dominantly by transmutation. Additionally, it further stresses the need to test ITER candidate Hall sensors under neutron flux with ITER relevant spectrum.

Duran, I. [Institute of Plasma Physics AS CR, v. v. i., Association EURATOM/IPP.CR, 182 00 Prague 8 (Czech Republic); Bolshakova, I.; Holyaka, R. [Magnetic Sensor Laboratory, Lviv Polytechnic National University, 790 31 Lviv (Ukraine); Viererbl, L.; Lahodova, Z. [Nuclear Research Institute plc., 250 68 Husinec-Rez (Czech Republic); Sentkerestiova, J. [Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, 115 19 Prague 1 (Czech Republic); Bem, P. [Nuclear Physics Institute AS CR, v. v. i., 250 68 Husinec-Rez (Czech Republic)

2010-10-15T23:59:59.000Z

379

Tritium processing system for the ITER Li/V blanket test module  

SciTech Connect (OSTI)

The purpose of the ITER Blanket Testing Module is to test the operating and performance of candidate blanket concepts under a real fusion environment. To assure fuel self-sufficiency the tritium breeding, recovery and processing have to be demonstrated. The tritium produced in the blanket has to be processed to a purity which can be used for refueling. All these functions need to be accomplished so that the tritium system can be scaled to a commercial fusion power plant from a safety and reliability point of view. This paper summarizes the tritium processing steps, the size of the equipment, power requirements, space requirements, etc. for a self-cooled lithium blanket. This information is needed for the design and layout of the test blanket ancillary system and to assure that the ITER guidelines for remote handling of ancillary equipment can be met.

Sze, D.K.; Hua, T.Q. [Argonne National Lab., IL (United States); Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Dagher, M.A.; Waganer, L.M.

1997-04-01T23:59:59.000Z

380

A Pseudo Random Numbers Generator Based on Chaotic Iterations. Application to Watermarking  

E-Print Network [OSTI]

In this paper, a new chaotic pseudo-random number generator (PRNG) is proposed. It combines the well-known ISAAC and XORshift generators with chaotic iterations. This PRNG possesses important properties of topological chaos and can successfully pass NIST and TestU01 batteries of tests. This makes our generator suitable for information security applications like cryptography. As an illustrative example, an application in the field of watermarking is presented.

Christophe Guyeux; Qianxue Wang; Jacques M. Bahi

2010-12-21T23:59:59.000Z

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

CHINA SPALLATION NEUTRON SOURCE PROJECT: DESIGN ITERATIONS AND R AND D STATUS.  

SciTech Connect (OSTI)

The China Spallation Neutron Source (CSNS) is an accelerator based high power project currently under preparation in China. The accelerator complex is based on an H{sup -} linear accelerator and a rapid cycling proton synchrotron. During the past year, the design of most accelerator systems went through major iterations, and initial research and developments were started on the prototyping of several key components. This paper summarizes major activities of the past year.

WEI,J.

2006-09-21T23:59:59.000Z

382

Absolutely and uniformly convergent iterative approach to inverse scattering with an infinite radius of convergence  

DOE Patents [OSTI]

A method and system for solving the inverse acoustic scattering problem using an iterative approach with consideration of half-off-shell transition matrix elements (near-field) information, where the Volterra inverse series correctly predicts the first two moments of the interaction, while the Fredholm inverse series is correct only for the first moment and that the Volterra approach provides a method for exactly obtaining interactions which can be written as a sum of delta functions.

Kouri, Donald J. (Houston, TX); Vijay, Amrendra (Houston, TX); Zhang, Haiyan (Houston, TX); Zhang, Jingfeng (Houston, TX); Hoffman, David K. (Ames, IA)

2007-05-01T23:59:59.000Z

383

Design of irradiation rig for reactor testing of prototype bolometers for ITER  

SciTech Connect (OSTI)

We describe the design of an experimental rig, which was developed to allow reactor testing at relevant conditions, i.e. vacuum and {approx}400 deg.C temperature, of prototype resistive bolometers, which will be used in ITER to acquire information on the radiated power distribution from the main plasma and in the diverter region. The main feature of the design is that the rig has no active temperature control. (authors)

Gusarov, A.; Huysmans, S. [SCK.CEN Belgian Nucrear Research Center, 2400 Mol (Belgium); Meister, H. [Max-Planck-Institut fuer Plasmaphysik, Boltzmannstr. 2, D-85748 Garching b. Muenchen (Germany); Hodgson, E. [Euratom/CIEMAT Fusion Association, Avenida Complutense 22, 28040 Madrid (Spain)

2011-07-01T23:59:59.000Z

384

Nested (inverse) binomial sums and new iterated integrals for massive Feynman diagrams  

E-Print Network [OSTI]

Nested sums containing binomial coefficients occur in the computation of massive operator matrix elements. Their associated iterated integrals lead to alphabets including radicals, for which we determined a suitable basis. We discuss algorithms for converting between sum and integral representations, mainly relying on the Mellin transform. To aid the conversion we worked out dedicated rewrite rules, based on which also some general patterns emerging in the process can be obtained.

Jakob Ablinger; Johannes Blümlein; Clemens G. Raab; Carsten Schneider

2014-07-17T23:59:59.000Z

385

Going with the group in a competitive game of iterated reasoning Seth Frey (sethfrey@indiana.edu)  

E-Print Network [OSTI]

Going with the group in a competitive game of iterated reasoning Seth Frey (sethfrey their strategy individually. John Nash proved that every game has at least one such equilib- rium. Mapped onto

Goldstone, Robert

386

Detailed search US supports Japanese bid to host ITER as France urges Europe to go it alone  

E-Print Network [OSTI]

support of his country for the Japanese bid to host the international thermonuclear site (ITER thermonuclear site if the French candidate is not selected for the international project. However

387

Report of a technical evaluation panel on the use of beryllium for ITER plasma facing material and blanket breeder material  

SciTech Connect (OSTI)

Beryllium because of its low atomic number and high thermal conductivity, is a candidate for both ITER first wall and divertor surfaces. This study addresses the following: why beryllium; design requirements for the ITER divertor; beryllium supply and unirradiated physical/mechanical property database; effects of irradiation on beryllium properties; tritium issues; beryllium health and safety; beryllium-coolant interactions and safety; thermal and mechanical tests; plasma erosion of beryllium; recommended beryllium grades for ITER plasma facing components; proposed manufacturing methods to produce beryllium parts for ITER; emerging beryllium materials; proposed inspection and maintenance techniques for beryllium components and coatings; time table and costs; and the importance of integrating materials and manufacturing personnel with designers.

Ulrickson, M.A. [ed.] [Sandia National Labs., Albuquerque, NM (United States); Manly, W.D. [Oak Ridge National Lab., TN (United States); Dombrowski, D.E. [Brush Wellman, Inc., Cleveland, OH (United States)] [and others

1995-08-01T23:59:59.000Z

388

White Paper for Developing Electromagnetic Particle Injector system for ITER on NSTX-U University of Washington (19 July 2012)  

E-Print Network [OSTI]

discharges in ITER, both the time response of this system and the controllability on demand - Conventional gas guns will inject gas before capsule and trigger pre rail gun We plan to finish the design during 2012 and to build

389

A competitive iterative procedure using a time-indexed model for ...  

E-Print Network [OSTI]

Aug 19, 2013 ... jobs, will thus serve to control the flow and stabilize its pace. This setting is not specific for the flexible job shop studied in this article, but is ...

2013-08-19T23:59:59.000Z

390

A model of constraint solvers by chaotic iteration adapted to value withdrawal explanations  

E-Print Network [OSTI]

of a value from a domain". This notion of explanation is essential for the debugging of CSP programs. Indeed of constraint programming is to solve Constraint Satisfaction Problems (CSP) [16], that is to provide constraint to the CSP. In future work, we plan to extend our framework in order to fully take labeling

Lesaint, Willy

391

An investigation into optimization of iteration parameters for solving partial differential equations by the alternating-direction implicit procedure  

E-Print Network [OSTI]

AN INVESTIGATION INTO OPTIMIZATION OF ITERATION PARAMETERS FOR SOLVING PARTIAL DIFFERENTIAL EQUATIONS BY THE ALTERNATING-DIRECTION IMPLICIT PROCEDURE A Thesis GERALD NELSON PITTS Submitted to the Graduate College of the Texas A&M University... in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE August 1967 Major Subject Com uter Science AN INVESTIGATION INTO OPTIMIZATION OF ITERATION PARAMETERS FOR SOLVING PARTIAL DIFFERENTIAL EQUATIONS BY THE ALTERNATING...

Pitts, Gerald Nelson

1967-01-01T23:59:59.000Z

392

Fast wave direct electron heating in advanced inductive and ITER baseline scenario discharges in DIII-D  

SciTech Connect (OSTI)

Fast Wave (FW) heating and electron cyclotron heating (ECH) are used in the DIII-D tokamak to study plasmas with low applied torque and dominant electron heating characteristic of burning plasmas. FW heating via direct electron damping has reached the 2.5 MW level in high performance ELMy H-mode plasmas. In Advanced Inductive (AI) plasmas, core FW heating was found to be comparable to that of ECH, consistent with the excellent first-pass absorption of FWs predicted by ray-tracing models at high electron beta. FW heating at the ?2 MW level to ELMy H-mode discharges in the ITER Baseline Scenario (IBS) showed unexpectedly strong absorption of FW power by injected neutral beam (NB) ions, indicated by significant enhancement of the D-D neutron rate, while the intended absorption on core electrons appeared rather weak. The AI and IBS discharges are compared in an effort to identify the causes of the different response to FWs.

Pinsker, R. I.; Jackson, G. L.; Luce, T. C.; Politzer, P. A. [General Atomics, PO Box 85608, San Diego, California 92186-5608 (United States); Austin, M. E. [University of Texas at Austin, Austin, Texas 78712 (United States); Diem, S. J.; Kaufman, M. C.; Ryan, P. M. [Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States); Doyle, E. J.; Zeng, L. [University of California Los Angeles, Los Angeles, California 90095 (United States); Grierson, B. A.; Hosea, J. C.; Nagy, A.; Perkins, R.; Solomon, W. M.; Taylor, G. [Princeton Plasma Physics Laboratory, Princeton, New Jersey 08543 (United States); Maggiora, R.; Milanesio, D. [Politecnico di Torino, Dipartimento di Elettronica, Torino (Italy); Porkolab, M. [Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); Turco, F. [Columbia University, New York, New York 10027 (United States)

2014-02-12T23:59:59.000Z

393

Fire Classifications Fires involving the ordinary  

E-Print Network [OSTI]

, plastics, etc. Fires involving combustible or flammable liquids such as gasoline, kerosene, oils, grease is protected by various devices such as smoke detectors, sprinkler systems, and manual fire alarm pull stations. Manual pull stations are strategically located throughout the University. Usually located by each exit

Jia, Songtao

394

Production of Meson Pairs Involving $L \  

E-Print Network [OSTI]

We present a formalism for studying the exclusive production or decay of mesons with any value of the internal orbital angular momentum L. As an application, we discuss the production of meson pairs (involving tensor and pseudotensor mesons) in photon-photon collisions.

Houra-Yaou, L; Parisi, J; Murgia, F; Hansson, J

1997-01-01T23:59:59.000Z

395

Environmental science and ecology involve studies  

E-Print Network [OSTI]

Environmental science and ecology involve studies of the biosphere, hydro- sphere, and lithosphere in environmental science is conducted on spatial scales varying from a single algal cell to the Earth as a whole's environmental scientists require investigation by an interdisciplinary team, including members from several

Christensen, Dan

396

Coupling the Mixed Potential and Radiolysis Models for Used Fuel Degradation  

SciTech Connect (OSTI)

The primary purpose of this report is to describe the strategy for coupling three process level models to produce an integrated Used Fuel Degradation Model (FDM). The FDM, which is based on fundamental chemical and physical principals, provides direct calculation of radionuclide source terms for use in repository performance assessments. The G-value for H2O2 production (Gcond) to be used in the Mixed Potential Model (MPM) (H2O2 is the only radiolytic product presently included but others will be added as appropriate) needs to account for intermediate spur reactions. The effects of these intermediate reactions on [H2O2] are accounted for in the Radiolysis Model (RM). This report details methods for applying RM calculations that encompass the effects of these fast interactions on [H2O2] as the solution composition evolves during successive MPM iterations and then represent the steady-state [H2O2] in terms of an “effective instantaneous or conditional” generation value (Gcond). It is anticipated that the value of Gcond will change slowly as the reaction progresses through several iterations of the MPM as changes in the nature of fuel surface occur. The Gcond values will be calculated with the RM either after several iterations or when concentrations of key reactants reach threshold values determined from previous sensitivity runs. Sensitivity runs with RM indicate significant changes in G-value can occur over narrow composition ranges. The objective of the mixed potential model (MPM) is to calculate the used fuel degradation rates for a wide range of disposal environments to provide the source term radionuclide release rates for generic repository concepts. The fuel degradation rate is calculated for chemical and oxidative dissolution mechanisms using mixed potential theory to account for all relevant redox reactions at the fuel surface, including those involving oxidants produced by solution radiolysis and provided by the radiolysis model (RM). The RM calculates the concentration of species generated at any specific time and location from the surface of the fuel. Several options being considered for coupling the RM and MPM are described in the report. Different options have advantages and disadvantages based on the extent of coding that would be required and the ease of use of the final product.

Buck, Edgar C.; Jerden, James L.; Ebert, William L.; Wittman, Richard S.

2013-08-30T23:59:59.000Z

397

Modeling  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

an implementation of a single-fluid inter- face model in the ALE-AMR code to simulate surface tension effects. The model does not require explicit information on the physical...

398

Regulation of the genes involved in nitrification.  

SciTech Connect (OSTI)

OAK-B135 This project focuses on the characterization of the regulation of the genes involved in nitrification in the bacterium Nitrosomonas europaea. The key genes in the nitrification pathway, amo and hao, are present in multiple copies in the genome. The promoters for these genes were identified and characterized. It was shown that there were some differences in the transcriptional regulation of the copies of these genes.

Arp, D.J.; Sayavedra-Soto, L.A.

2003-08-14T23:59:59.000Z

399

US ITER  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation InInformation InExplosion Monitoring:Home|Physics ResearchLCLS Sign Register today for

400

US ITER  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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to obtain the most current and comprehensive results.


401

X-ray crystal spectrometer upgrade for ITER-like wall experiments at JET  

SciTech Connect (OSTI)

The high resolution X-Ray crystal spectrometer at the JET tokamak has been upgraded with the main goal of measuring the tungsten impurity concentration. This is important for understanding impurity accumulation in the plasma after installation of the JET ITER-like wall (main chamber: Be, divertor: W). This contribution provides details of the upgraded spectrometer with a focus on the aspects important for spectral analysis and plasma parameter calculation. In particular, we describe the determination of the spectrometer sensitivity: important for impurity concentration determination.

Shumack, A. E., E-mail: amy.shumack@ccfe.ac.uk [JET-EFDA, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); FOM Institute DIFFER, P.O. Box 1207, NL-3430 BE Nieuwegein (Netherlands); Rzadkiewicz, J. [National Centre for Nuclear Research, Andrzeja So?tana 7, 05-400 Otwock (Poland); Chernyshova, M.; Czarski, T.; Karpinski, L. [Institute of Plasma Physics and Laser Microfusion, Hery 23, 01-497 Warsaw (Poland); Jakubowska, K. [Institute of Plasma Physics and Laser Microfusion, Hery 23, 01-497 Warsaw (Poland); Université Bordeaux, CNRS, CEA, CELIA, UMR 5107, F-33405 Talence (France); Scholz, M. [Institute of Nuclear Physics PAN, ul. Radzikowskiego 152, 31-342 Kraków (Poland); Byszuk, A.; Cieszewski, R.; Kasprowicz, G.; Pozniak, K.; Wojenski, A.; Zabolotny, W. [Institute of Electronic Systems, Warsaw University of Technology, 00-665 Warsaw (Poland); Dominik, W. [Faculty of Physics, Institute of Experimental Physics, Warsaw University, 00-681 Warsaw (Poland); Conway, N. J.; Dalley, S.; Tyrrell, S.; Zastrow, K.-D. [JET-EFDA, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Figueiredo, J. [EFDA-CSU, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Associação EURATOM/IST, Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Av Rovisco Pais, 1049-001 Lisbon (Portugal); and others

2014-11-15T23:59:59.000Z

402

Alpha Heating in ITER L-mode and H-mode Plasma  

SciTech Connect (OSTI)

There are many uses of predictions of ITER plasma performance. One is assessing requirements of different plasma regimes. For instance, what current drive and control are needed for steady state. The heating, current drive, and torque systems planned for initial DT operation are negative ion neutral beam injection (NB), ion cyclotron resonance (IC), and electron cyclotron resonance (EC). Which combinations of heating are optimal. What are benefits of the torques, current drive, and fueling using NB. What are the shine-through power and optimum voltage for the NB? What are optimal locations and aiming of the EC launchers? Another application is nuclear licensing (e.g. System integrity, how many neutrons).

R.V. Budny

2011-07-18T23:59:59.000Z

403

SPARSE REPRESENTATIONS WITH DATA FIDELITY TERM VIA AN ITERATIVELY REWEIGHTED LEAST SQUARES ALGORITHM  

SciTech Connect (OSTI)

Basis Pursuit and Basis Pursuit Denoising, well established techniques for computing sparse representations, minimize an {ell}{sup 2} data fidelity term subject to an {ell}{sup 1} sparsity constraint or regularization term on the solution by mapping the problem to a linear or quadratic program. Basis Pursuit Denoising with an {ell}{sup 1} data fidelity term has recently been proposed, also implemented via a mapping to a linear program. They introduce an alternative approach via an iteratively Reweighted Least Squares algorithm, providing greater flexibility in the choice of data fidelity term norm, and computational advantages in certain circumstances.

WOHLBERG, BRENDT [Los Alamos National Laboratory; RODRIGUEZ, PAUL [Los Alamos National Laboratory

2007-01-08T23:59:59.000Z

404

Robust parallel iterative solvers for linear and least-squares problems, Final Technical Report  

SciTech Connect (OSTI)

The primary goal of this project is to study and develop robust iterative methods for solving linear systems of equations and least squares systems. The focus of the Minnesota team is on algorithms development, robustness issues, and on tests and validation of the methods on realistic problems. 1. The project begun with an investigation on how to practically update a preconditioner obtained from an ILU-type factorization, when the coefficient matrix changes. 2. We investigated strategies to improve robustness in parallel preconditioners in a specific case of a PDE with discontinuous coefficients. 3. We explored ways to adapt standard preconditioners for solving linear systems arising from the Helmholtz equation. These are often difficult linear systems to solve by iterative methods. 4. We have also worked on purely theoretical issues related to the analysis of Krylov subspace methods for linear systems. 5. We developed an effective strategy for performing ILU factorizations for the case when the matrix is highly indefinite. The strategy uses shifting in some optimal way. The method was extended to the solution of Helmholtz equations by using complex shifts, yielding very good results in many cases. 6. We addressed the difficult problem of preconditioning sparse systems of equations on GPUs. 7. A by-product of the above work is a software package consisting of an iterative solver library for GPUs based on CUDA. This was made publicly available. It was the first such library that offers complete iterative solvers for GPUs. 8. We considered another form of ILU which blends coarsening techniques from Multigrid with algebraic multilevel methods. 9. We have released a new version on our parallel solver - called pARMS [new version is version 3]. As part of this we have tested the code in complex settings - including the solution of Maxwell and Helmholtz equations and for a problem of crystal growth.10. As an application of polynomial preconditioning we considered the problem of evaluating f(A)v which arises in statistical sampling. 11. As an application to the methods we developed, we tackled the problem of computing the diagonal of the inverse of a matrix. This arises in statistical applications as well as in many applications in physics. We explored probing methods as well as domain-decomposition type methods. 12. A collaboration with researchers from Toulouse, France, considered the important problem of computing the Schur complement in a domain-decomposition approach. 13. We explored new ways of preconditioning linear systems, based on low-rank approximations.

Saad, Yousef

2014-01-16T23:59:59.000Z

405

Concept development for the ITER equatorial port visible/infrared wide angle viewing system  

SciTech Connect (OSTI)

The ITER equatorial port visible/infrared wide angle viewing system concept is developed from the measurement requirements. The proposed solution situates 4 viewing systems in the equatorial ports 3, 9, 12, and 17 with 4 views each (looking at the upper target, the inner divertor, and tangentially left and right). This gives sufficient coverage. The spatial resolution of the divertor system is 2 times higher than the other views. For compensation of vacuum-vessel movements, an optical hinge concept is proposed. Compactness and low neutron streaming is achieved by orienting port plug doglegs horizontally. Calibration methods, risks, and R and D topics are outlined.

Reichle, R.; Beaumont, B.; Boilson, D.; Bouhamou, R.; Direz, M.-F.; Encheva, A.; Henderson, M.; Kazarian, F.; Lamalle, Ph.; Lisgo, S.; Mitteau, R.; Patel, K. M.; Pitcher, C. S.; Pitts, R. A.; Prakash, A.; Raffray, R.; Schunke, B.; Snipes, J.; Diaz, A. Suarez; Udintsev, V. S. [ITER Organization, Route de Vinon-sur-Verdon, 13115 St Paul-lez-Durance (France); and others

2012-10-15T23:59:59.000Z

406

Large-order shifted 1/N expansions through the asymptotic iteration method  

E-Print Network [OSTI]

The perturbation technique within the framework of the asymptotic iteration method is used to obtain large-order shifted 1/N expansions, where N is the number of spatial dimensions. This method is contrary to the usual Rayleigh-Schr\\"{o}dinger perturbation theory, no matrix elements need to be calculated. The method is applied to the Schr\\"{o}dinger equation and the non-polynomial potential $V(r)=r^2+\\frac{b r^2}{(1+cr^2)}$ in three dimensions is discussed as an illustrative example.

T. Barakat

2007-08-16T23:59:59.000Z

407

US ITER is a strong contributor in plan to enhance international sharing of  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIA Energy Conference U.S. Crude OilITER Movingprime

408

Inter-Machine Comparison of the Termination Phase and Energy Conversion in Tokamak Disruptions with Runaway Current Plateau Formation and Implications for ITER  

E-Print Network [OSTI]

Inter-Machine Comparison of the Termination Phase and Energy Conversion in Tokamak Disruptions with Runaway Current Plateau Formation and Implications for ITER

409

Tungsten Divertor Erosion in all Metal Devices: Lessons from the ITER-Like Wall of JET and the All Tungsten ASDEX Upgrade  

E-Print Network [OSTI]

Tungsten Divertor Erosion in all Metal Devices: Lessons from the ITER-Like Wall of JET and the All Tungsten ASDEX Upgrade

410

Simulation of Tungsten Sputtering with EDGE2D-EIRENE in Low Triangularity L-Mode JET ITER-Like Wall Configuration  

E-Print Network [OSTI]

Simulation of Tungsten Sputtering with EDGE2D-EIRENE in Low Triangularity L-Mode JET ITER-Like Wall Configuration

411

Community Involvement | Y-12 National Security Complex  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series to User Group and UserofProteinNews CommunicationsInvolvement Community

412

Community Involvement and Making a Difference  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New SubstationCleanCommunity Involvement and Making a Difference Community

413

Choice, involvement and illusory control 1 Running head: CHOICE, INVOLVEMENT AND ILLUSORY CONTROL  

E-Print Network [OSTI]

, which triggers the (quasi-)immediate resolution of the gamble (e.g., spinning the wheel, throwing the dice, picking the ball from the urn).1 Choice and Involvement are orthogonal dimensions of the gambling

Boyer, Edmond

414

Beryllium fabrication/cost assessment for ITER (International Thermonuclear Experimental Reactor)  

SciTech Connect (OSTI)

A fabrication and cost estimate of three possible beryllium shapes for the International Thermonuclear Experimental Reactor (ITER) blanket is presented. The fabrication method by hot pressing (HP), cold isostatic pressing plus sintering (CIP+S), cold isostatic pressing plus sintering plus hot isostatic pressing (CIP+S+HIP), and sphere production by atomization or rotary electrode will be discussed. Conventional hot pressing blocks of beryllium with subsequent machining to finished shapes can be more expensive than production of a net shape by cold isostatic pressing and sintering. The three beryllium shapes to be considered here and proposed for ITER are: (1) cubic blocks (3 to 17 cm on an edge), (2) tubular cylinders (33 to 50 mm i.d. by 62 mm o.d. by 8 m long), and (3) spheres (1--5 mm dia.). A rough cost estimate of the basic shape is presented which would need to be refined if the surface finish and tolerances required are better than the sintering process produces. The final cost of the beryllium in the blanket will depend largely on the machining and recycling of beryllium required to produce the finished product. The powder preparation will be discussed before shape fabrication. 10 refs., 6 figs.

Beeston, J.M. (Beeston (J.M.), Garrison, UT (USA)); Longhurst, G.R. (EG and G Idaho, Inc., Idaho Falls, ID (USA)); Parsonage, T. (Brush Wellman, Inc., Elmore, OH (USA))

1990-06-01T23:59:59.000Z

415

A Fast Exhaust-Gas Analyzer for the ITER Fusion Experiment Divertor  

SciTech Connect (OSTI)

This paper presents a first demonstration of a radio-frequency (RF)-excited optical gas analyzer (RF-OGA) designed to quantitatively measure minority species inside the neutralization region of the ITER fusion experiment divertor. The sensor head, which creates its own plasma excitation and plasma light emission, is designed to operate in a strong magnetic field, and the RF coupling leads to bright light emission. It also allows for operation at low voltages, avoiding the radiation-enhanced breakdowns expected when high voltages are present in the ITER environment. Furthermore, the preferred sensor head features full isolation of the metal RF electrodes from the induced plasma. This "electrodeless" operation will permit long operation without frequent maintenance. The testing of a first experimental RF-OGA with an electrodeless design in a strong (similar to 2-T) magnetic field showed a mostly linear response of the He I-6678 angstrom line emission to the He concentration in a hydrogen background, which would produce a He concentration measurement accurate to within 2% of the helium-to-hydrogen ratio.

Klepper, C Christopher [ORNL; Carlson, E. P. [HY Tech Research Corporation; Moschella, J. J. [HY Tech Research Corporation; Hazelton, R C [Hy-Tech Research Corporation; Keitz, M D [Hy-Tech Research Corporation; Gardner, Walter L [ORNL

2010-01-01T23:59:59.000Z

416

Efficient iterative method for solving the Dirac-Kohn-Sham density functional theory  

SciTech Connect (OSTI)

We present for the first time an efficient iterative method to directly solve the four-component Dirac-Kohn-Sham (DKS) density functional theory. Due to the existence of the negative energy continuum in the DKS operator, the existing iterative techniques for solving the Kohn-Sham systems cannot be efficiently applied to solve the DKS systems. The key component of our method is a novel filtering step (F) which acts as a preconditioner in the framework of the locally optimal block preconditioned conjugate gradient (LOBPCG) method. The resulting method, dubbed the LOBPCG-F method, is able to compute the desired eigenvalues and eigenvectors in the positive energy band without computing any state in the negative energy band. The LOBPCG-F method introduces mild extra cost compared to the standard LOBPCG method and can be easily implemented. We demonstrate our method in the pseudopotential framework with a planewave basis set which naturally satisfies the kinetic balance prescription. Numerical results for Pt$_{2}$, Au$_{2}$, TlF, and Bi$_{2}$Se$_{3}$ indicate that the LOBPCG-F method is a robust and efficient method for investigating the relativistic effect in systems containing heavy elements.

Lin, Lin; Shao, Sihong; E, Weinan

2012-11-06T23:59:59.000Z

417

Recent Advances on Hydrogenic Retention in ITER's Plasma-Facing Materials: BE, C, W.  

SciTech Connect (OSTI)

Management of tritium inventory remains one of the grand challenges in the development of fusion energy and the choice of plasma-facing materials is a key factor for in-vessel tritium retention. The Atomic and Molecular Data Unit of the International Atomic Energy Agency organized a Coordinated Research Project (CRP) on the overall topic of tritium inventory in fusion reactors during the period 2001-2006. This dealt with hydrogenic retention in ITER's plasma-facing materials, Be, C, W, and in compounds (mixed materials) of these elements as well as tritium removal techniques. The results of the CRP are summarized in this article together with recommendations for ITER. Basic parameters of diffusivity, solubility and trapping in Be, C and W are reviewed. For Be, the development of open porosity can account for transient hydrogenic pumping but long term retention will be dominated by codeposition. Codeposition is also the dominant retention mechanism for carbon and remains a serious concern for both Be and C containing layers. Hydrogenic trapping in unirradiated tungsten is low but will increase with ion and neutron damage. Mixed materials will be formed in a tokamak and these can also retain significant amounts of hydrogen isotopes. Oxidative and photon-based techniques for detritiation of plasma-facing components are described.

Skinner, C H; Alimov, Kh; Bekris, N; Causey, R A; Clark, R.E.H.; Coad, J P; Davis, J W; Doerner, R P; Mayer, M; Pisarev, A; Roth, J; Tanabe, T

2008-03-29T23:59:59.000Z

418

Characterization of TFTR shielding penetrations of ITER-relevance in D-T neutron field  

SciTech Connect (OSTI)

D-T operation of TFTR began successfully with trace tritium discharges in mid-November 1993. During the next year, the TFTR plasma tritium fraction is scheduled to be increased to at least 50%. The availability of larger amounts of D-T fusion neutrons in the high power D-T plasma phase of TFTR provides a useful opportunity to characterize tokamak shielding-penetration geometries of potential interest to ITER. These types of measurements can provide direct experimental data on the degree of enhancement of transmitted neutron flux along or across a realistic penetration and, as such, can be used to validate, calculational methods and to meet fusion reactor licensing requirements. The enhancement of neutron streaming in the shielding penetrations has the following significant consequences from the ITER viewpoint: (1) increased radiation damage to plasma diagnostics/detectors, (2) increased biological dose rates behind the shield, (3) increased radiation damage to the superconducting magnet on the inboard side. TFTR has penetrations of different varieties inside the vacuum vessel, the test cell, and the adjoining hot cell. In the initial stage, the authors have chosen to characterize three different types of penetrations in and around the TFTR test cell: (1) a straight hollow pipe coming out of the test cell concrete wall on east side of the test cell into the hot cell, (2) a bent pipe coming out of the test cell through the north concrete wall, and (3) a labyrinth in the north-west end of the test cell.

Kumar, A.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Kugel, H.W. [Princeton Univ., NJ (United States)

1994-12-31T23:59:59.000Z

419

Worker Involvement Improves Safety at Hanford Site's Plutonium...  

Broader source: Energy.gov (indexed) [DOE]

Worker Involvement Improves Safety at Hanford Site's Plutonium Finishing Plant Worker Involvement Improves Safety at Hanford Site's Plutonium Finishing Plant May 29, 2014 - 12:00pm...

420

Modeling  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

a single-fluid diffuse interface model in the ALE-AMR hydrodynamics code to simulate surface tension effects. We show simula- tions and compare them to other surface tension...

Note: This page contains sample records for the topic "model involves iterative" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Modeling  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

sion effects. We show the result of a test case, and compare it to the result without surface tension. The model describes droplet formation nicely. Application The ARRA-funded...

422

Apolipoprotein gene involved in lipid metabolism  

DOE Patents [OSTI]

Methods and materials for studying the effects of a newly identified human gene, APOAV, and the corresponding mouse gene apoAV. The sequences of the genes are given, and transgenic animals which either contain the gene or have the endogenous gene knocked out are described. In addition, single nucleotide polymorphisms (SNPs) in the gene are described and characterized. It is demonstrated that certain SNPs are associated with diseases involving lipids and triglycerides and other metabolic diseases. These SNPs may be used alone or with SNPs from other genes to study individual risk factors. Methods for intervention in lipid diseases, including the screening of drugs to treat lipid-related or diabetic diseases are also disclosed.

Rubin, Edward (Berkeley, CA); Pennacchio, Len A. (Sebastopol, CA)

2007-07-03T23:59:59.000Z

423

SOLID BREEDER BLANKET OPTION FOR THE ITER CONCEPTUAL DESIGN* Y. Cohar, H. Attaya, M.C. Billone, P. Finn, S. Majumdar, L.R. Turner  

E-Print Network [OSTI]

SOLID BREEDER BLANKET OPTION FOR THE ITER CONCEPTUAL DESIGN* Y. Cohar, H. Attaya, M.C. Billone, P in this paper. lntroduction A solid-breeder water-cooled blanket option was developed for ITER based lithium-6 enrichment reduces the solid breeder volume required in the blanket and the total tritium

Raffray, A. René

424

RAMI Analysis for Designing and Optimizing Tokamak Cooling Water System (TCWS) for the ITER's Fusion Reactor  

SciTech Connect (OSTI)

U.S.-ITER is responsible for the design, engineering, and procurement of the Tokamak Cooling Water System (TCWS). TCWS is designed to provide cooling and baking for client systems that include the first wall/blanket, vacuum vessel, divertor, and neutral beam injector. Additional operations that support these primary functions include chemical control of water provided to client systems, draining and drying for maintenance, and leak detection/localization. TCWS interfaces with 27 systems including the secondary cooling system, which rejects this heat to the environment. TCWS transfers heat generated in the Tokamak during nominal pulsed operation - 850 MW at up to 150 C and 4.2 MPa water pressure. Impurities are diffused from in-vessel components and the vacuum vessel by water baking at 200-240 C at up to 4.4 MPa. TCWS is complex because it serves vital functions for four primary clients whose performance is critical to ITER's success and interfaces with more than 20 additional ITER systems. Conceptual design of this one-of-a-kind cooling system has been completed; however, several issues remain that must be resolved before moving to the next stage of the design process. The 2004 baseline design indicated cooling loops that have no fault tolerance for component failures. During plasma operation, each cooling loop relies on a single pump, a single pressurizer, and one heat exchanger. Consequently, failure of any of these would render TCWS inoperable, resulting in plasma shutdown. The application of reliability, availability, maintainability, and inspectability (RAMI) tools during the different stages of TCWS design is crucial for optimization purposes and for maintaining compliance with project requirements. RAMI analysis will indicate appropriate equipment redundancy that provides graceful degradation in the event of an equipment failure. This analysis helps demonstrate that using proven, commercially available equipment is better than using custom-designed equipment with no field experience and lowers specific costs while providing higher reliability. This paper presents a brief description of the TCWS conceptual design and the application of RAMI tools to optimize the design at different stages during the project.

Ferrada, Juan J [ORNL] [ORNL; Reiersen, Wayne T [ORNL] [ORNL

2011-01-01T23:59:59.000Z

425

Modelling  

E-Print Network [OSTI]

Modeling of technical machines became a standard technique since computer became powerful enough to handle the amount of data relevant to the specific system. Simulation of an existing physical device requires the knowledge of all relevant quantities. Electric fields given by the surrounding boundary as well as magnetic fields caused by coils or permanent magnets have to be known. Internal sources for both fields are sometimes taken into account, such as space charge forces or the internal magnetic field of a moving bunch of charged particles. Used solver routines are briefly described and some bench-marking is shown to estimate necessary computing times for different problems. Different types of charged particle sources will be shown together with a suitable model to describe the physical model. Electron guns are covered as well as different ion sources (volume ion sources, laser ion sources, Penning ion sources, electron resonance ion sources, and H$^-$-sources) together with some remarks on beam transport.

Spädtke, P

2013-01-01T23:59:59.000Z

426

An Algorithm for Nonparametric GARCH Modelling Peter Buhlmann  

E-Print Network [OSTI]

An Algorithm for Nonparametric GARCH Modelling Peter BË?uhlmann Seminar fË?ur Statistik Federal propose a simple iterative algorithm for nonparametric first­order GARCH modelling. This method o#ers an alternative to fitting one of the many di#er­ ent parametric GARCH specifications that have been proposed

Buehlmann, Peter

427

Using Process Modeling for Process Understanding Dewayne E. Perry  

E-Print Network [OSTI]

Using Process Modeling for Process Understanding Dewayne E. Perry Systems and Software Research to improving processes is first understanding them. I report here a case study in process understanding using the process modeling language Interact. I illustrate both the language and the process iteratively, somewhat

Perry, Dewayne E.

428

The development of in-situ calibration method for divertor IR thermography in ITER  

SciTech Connect (OSTI)

For the development of the calibration method of the emissivity in IR light on the divertor plate in ITER divertor IR thermography system, the laboratory experiments have been performed by using IR instruments. The calibration of the IR camera was performed by the plane black body in the temperature of 100–600 degC. The radiances of the tungsten heated by 280 degC were measured by the IR camera without filter (2.5–5.1 ?m) and with filter (2.95 ?m, 4.67 ?m). The preliminary data of the scattered light of the laser of 3.34 ?m that injected into the tungsten were acquired.

Takeuchi, M.; Sugie, T.; Ogawa, H.; Takeyama, S.; Itami, K. [Japan Atomic Energy Agency (Japan)

2014-08-21T23:59:59.000Z

429

Design Analysis and Manufacturing Studies for ITER In-Vessel Coils  

SciTech Connect (OSTI)

ITER is incorporating two types of In Vessel Coils (IVCs): ELM Coils to mitigate Edge Localized Modes and VS Coils to provide Vertical Stabilization of the plasma. Strong coupling with the plasma is required so that the ELM and VS Coils can meet their performance requirements. Accordingly, the IVCs are in close proximity to the plasma, mounted just behind the Blanket Shield Modules. This location results in a radiation and temperature environment that is severe necessitating new solutions for material selection as well as challenging analysis and design solutions. Fitting the coil systems in between the blanket shield modules and the vacuum vessel leads to difficult integration with diagnostic cabling and cooling water manifolds.

Kalish, M.; Heitzenroeder, P.; Neumeyer, C.; Titus, P.; Zhai, Y.; Zatz, I.; Messineo, M.; Gomez, M.; Hause, C. [Princeton Plasma Physics Lab., Princeton, NJ (United States); Daly, E.; Martin, A. [ITER Organization, St. Paul-lez-Duranace (France); Wu, Y.; Jin, J.; Long, F.; Song, Y.; Wang, Z.; Yun, Zan [Chinese Academy of Sciences, Anhui (China). Institute of Plasma Physics; Hsiao, J. [Vector Resources, Annandale, VA (United States); Pillsbury, J. R. [Sherbrooke Consulting, Arlington, VA (United States); Bohm, T.; Sawan, M. [Univ. of Wisconsin-Madison, WI (United States). Fustion Technology Institute; Jiang, NFN [Southwestern Institute of Physics, Chengdu (China)

2014-07-01T23:59:59.000Z

430

Neutronics Experiments Using Small Partial Mockups of the ITER Test Blanket Module with a Solid Breeder  

SciTech Connect (OSTI)

In order to evaluate the impacts of the incident neutron spectrum and the tungsten armor on the tritium production, integral experiments have been performed with small partial mockups relevant to the ITER test blanket module using DT neutrons at FNS of JAERI. The Monte Carlo calculation results for the integrated tritium productions agree well with the experimental data within 2 and 11 % for the mockups without the armor in the experiments without and with the neutron reflector, respectively. It is clarified that the tritium production can be very accurately predicted in the experiment without the reflector. In the mockups with the 12.6 and 25.2 mm thick tungsten armors, it is experimentally clarified that the integrated tritium productions are reduced by 3 and 6 % relative to the case without the armor, respectively.

Sato, Satoshi; Verzilov, Yury; Nakao, Makoto; Ochiai, Kentaro; Wada, Masayuki; Nishitani, Takeo [Japan Atomic Energy Research Institute (Japan)

2005-05-15T23:59:59.000Z

431

Conceptual design of the collection optics for the edge Thomson scattering system in ITER  

SciTech Connect (OSTI)

Neutron and gamma-ray irradiation complicates the design of the edge Thomson scattering (TS) system in ITER. The TS light is relayed through the relaying optics with labyrinth and fiber coupling optics. Electron density of 2x10{sup 19} m{sup -3} is sufficient to measure T{sub e} and n{sub e} within a 10% and 5% margin of error, respectively, with a spatial resolution of 5 mm. This system can cover from 0.85 to 1 of the normalized minor radius. The time resolution is 10 ms, which is determined by the repetition rate of the laser device. A super-Gaussian is the ideal laser profile for the laser injection optics to avoid a breakdown of the filling gas used in density calibration through Raman scattering.

Yatsuka, E.; Hatae, T.; Kusama, Y. [Japan Atomic Energy Agency, Naka, Ibaraki 311-0193 (Japan); Suitoh, S.; Aida, Y. [Showa Optronics Co., Ltd., Yokohama, Kanagawa 226-0006 (Japan)

2010-10-15T23:59:59.000Z

432

Progress of the ITER equatorial vis/IR wide angle viewing system optical design  

SciTech Connect (OSTI)

The equatorial vis/IR wide angle viewing system is present in four ITER diagnostic equatorial ports. This instrument will cover a large field of view with high spatial and temporal resolutions, to provide real time temperature measurements of plasma facing components, spectral data in the visible range, information on runaway electrons, and pellet tracking. This diagnostic needs to be reliable, precise, and long lasting. Its design is driven by both the tokamak severe environment and the high performances required for machine protection. The preliminary design phase is ongoing. Paramount issues are being tackled, relative to wide spectral band optical design, material choice, and optomechanical difficulties due to the limited space available for this instrument in the ports, since many other diagnostics and services are also present. Recent progress of the diagnostic optical design and status of associated R and D are presented.

Davi, M.; Corre, Y.; Guilhem, D.; Jullien, F.; Reichle, R.; Salasca, S.; Travere, J. M. [Association Euratom CEA, CEA/DSM/IRFM, Cadarache, 13108 Saint-Paul-lez-Durance (France); Cal, E. de la; Manzanares, A.; Pablos, J. L. de [Association Euratom CIEMAT, Av. Complutense 22, 28040 Madrid (Spain); Migozzi, J. B. [JBM Optique, 11 Av. de la division Leclerc, 92310 Sevres (France)

2008-10-15T23:59:59.000Z

433

Loca study for a helium-cooled solid breeder design for ITER  

SciTech Connect (OSTI)

The analysis of thermal processes after a loss-of-coolant accident (LOCA) in a solid breeder blanket is important because of the first wall and solid breeder maximum allowable temperature constraints. The objective is to design for a LOCA so that following a LOCA, the maximum solid breeder and structure temperatures are less than the limit beyond which irreversible damage is done, which would lead to loss of investment. The temporal temperature profiles for the solid breeder and first wall regions of a helium-cooled solid breeder design for ITER were calculated based on afterheat values for adiabatic and non-adiabatic conditions and the results are presented in this paper. It is found that, for this design, even when excluding radiation to the cooled inboard, a LOCA can be recommended by energy removal through a flowing purge with a reasonable flow rate.

Gorbis, Z.R.; Raffray, A.R.; Fujimura, K.; Jun, I.; Abdou, M.A.

1989-03-01T23:59:59.000Z

434

Genomic Aspects of Research Involving Polyploid Plants  

SciTech Connect (OSTI)

Almost all extant plant species have spontaneously doubled their genomes at least once in their evolutionary histories, resulting in polyploidy which provided a rich genomic resource for evolutionary processes. Moreover, superior polyploid clones have been created during the process of crop domestication. Polyploid plants generated by evolutionary processes and/or crop domestication have been the intentional or serendipitous focus of research dealing with the dynamics and consequences of genome evolution. One of the new trends in genomics research is to create synthetic polyploid plants which provide materials for studying the initial genomic changes/responses immediately after polyploid formation. Polyploid plants are also used in functional genomics research to study gene expression in a complex genomic background. In this review, we summarize the recent progress in genomics research involving ancient, young, and synthetic polyploid plants, with a focus on genome size evolution, genomics diversity, genomic rearrangement, genetic and epigenetic changes in duplicated genes, gene discovery, and comparative genomics. Implications on plant sciences including evolution, functional genomics, and plant breeding are presented. It is anticipated that polyploids will be a regular subject of genomics research in the foreseeable future as the rapid advances in DNA sequencing technology create unprecedented opportunities for discovering and monitoring genomic and transcriptomic changes in polyploid plants. The fast accumulation of knowledge on polyploid formation, maintenance, and divergence at whole-genome and subgenome levels will not only help plant biologists understand how plants have evolved and diversified, but also assist plant breeders in designing new strategies for crop improvement.

Yang, Xiaohan [ORNL; Ye, Chuyu [ORNL; Tschaplinski, Timothy J [ORNL; Wullschleger, Stan D [ORNL; Tuskan, Gerald A [ORNL

2011-01-01T23:59:59.000Z

435

A successful effort to involve stakeholders in a facility siting decision using LIPS with stakeholder involvement  

SciTech Connect (OSTI)

Local public opposition to federal bureaucratic decisions has resulted in public agencies rethinking the role of stakeholders in decision making. Efforts to include stakeholders directly in the decision-making process are on the increase. Unfortunately, many attempts to involve members of the public in decisions involving complex technical issues have failed. A key problem has been defining a meaningful role for the public in the process of arriving at a technical decision. This paper describes a successful effort by Sandia National Laboratories (SNL) in New Mexico to involve stakeholders in an important technical decision associated with its Environmental Restoration (ER) Project. The decision was where to locate a Corrective Action Management Unit (CAMU), a facility intended to consolidate and store wastes generated from the cleanup of hazardous waste sites. A formal priority setting process known as the Laboratory Integration Prioritization System (LIPS) was adapted to provide an approach for involving the public. Although rarely applied to stakeholder participation, the LIPS process proved surprisingly effective. It produced a consensus over a selected site and enhanced public trust and understanding of Project activities.

Merkhofer, L. [Applied Decision Analysis, Inc., Menlo Park, CA (United States); Conway, R. [Sandia National Labs., Albuquerque, NM (United States); Anderson, B. [Los Alamos National Lab., NM (United States)

1995-12-31T23:59:59.000Z

436

IAEA FEC Saint Petersburg, Russia, 13-18 October 2014, O. Motojima The ITER Project Construction Status  

E-Print Network [OSTI]

IAEA FEC Saint Petersburg, Russia, 13-18 October 2014, O. Motojima Slide 1/14 OM14755 The ITER Project Construction Status IAEA FEC 13 to 18 October, 2014 Saint Petersburg, Russia Osamu Motojima President Barroso (11 July 2014) #12;IAEA FEC Saint Petersburg, Russia, 13-18 October 2014, O. Motojima

437

Absolute x-ray energy calibration over a wide energy range using a diffraction-based iterative method  

E-Print Network [OSTI]

Mineral Physics Institute, Stony Brook University, Stony Brook, New York 11794, USA 2 DepartmentAbsolute x-ray energy calibration over a wide energy range using a diffraction-based iterative;REVIEW OF SCIENTIFIC INSTRUMENTS 83, 063901 (2012) Absolute x-ray energy calibration over a wide energy

Duffy, Thomas S.

438

Exhibit 1B Patent Rights Acquisition by the Government ITER UT-B Contracts Div Page 1 of 6  

E-Print Network [OSTI]

of Energy patent waiver regulations at 10 CFR Part 784. (6) "Agency licensing regulations" and "applicable regulations at 10 CFR Part 781. (7) "Member" means members of the ITER Organization who are parties Organization composed of Representatives of the Members and as described in Article 6 of the Agreement. (10

Pennycook, Steve

439

Spain offers a total of 900 Millions Spain proposes to double her contribution to host ITER, the experimental fusion  

E-Print Network [OSTI]

Spain offers a total of 900 Millions Spain proposes to double her contribution to host ITER commission Romani Prodi and the rotating presidency of the European Union, held by Italy, that Spain. The science and technology minister, Juan Costa, stated that Spain is now willing to contribute 20

440

Iterative Modellerstellung mit Siemens IDATG Das Siemens IDATG (Integrating Design and Automated Testcase Generation) Tool erlaubt eine  

E-Print Network [OSTI]

Iterative Modellerstellung mit Siemens IDATG Das Siemens IDATG (Integrating Design:http://www.ist.tugraz.at/staff/peischl Dipl.Ing. Armin Beer Support Center Test Siemens PSE Gudrunstrasse 11 1100 Wien Tel.: +43 51707 43 342 mailto: armin.beer@siemens.com web: http://www.siemens.com #12;

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441

Tuesday April 12, 8:14 PM LEAD: Japan, EU aim to reach conclusion on ITER by July  

E-Print Network [OSTI]

Tuesday April 12, 8:14 PM LEAD: Japan, EU aim to reach conclusion on ITER by July (Kyodo) _ (EDS." Earlier in the day, Potocnik met with Japan's Education, Culture, Sports, Science and Technology Minister: UPDATING WITH EU COMMISSIONER'S PRESS CONFERENCE) Japan and the European Union agreed Tuesday to speed up

442

AN ASSESSMENT OF THE BASE BLANKETFOR ITER A. R. Raffray, M. A, Abdou, and A. Ying, Mechanical, Aerospace and Nuclear  

E-Print Network [OSTI]

Ideally, the ITER base blanket would provide the necessary tritium for the reactor to be self-sufficientduring operation, while having minimal impact on the overall reactor cost, reliability and safety.A solid breeder blanket has been developed in the CDA phase in an attemptto achieve such objectives

Abdou, Mohamed

443

THERMOMECHANICAL ANALYSIS OF THE REVISED U.S. ITER DCLL TEST BLANKET MODULE Aaron T. Aoyama1  

E-Print Network [OSTI]

wall and blanket structure, and the self-cooled Pb-17Li breeder is circulated for power conversion and blanket, and self-cooled Pb-17Li breeder circulated for power conversion and tritium extraction. A midTHERMOMECHANICAL ANALYSIS OF THE REVISED U.S. ITER DCLL TEST BLANKET MODULE Aaron T. Aoyama1

Ghoniem, Nasr M.

444

SUMBMISSION TO TPAMI: OOI EXTRACTION BY LOCAL-GLOBAL ENERGY MINIMIZATION 1 Iterative local-global energy minimization for  

E-Print Network [OSTI]

SUMBMISSION TO TPAMI: OOI EXTRACTION BY LOCAL-GLOBAL ENERGY MINIMIZATION 1 Iterative local-global energy minimization for automatic extraction of object of interest Gang Hua, Member, IEEE, Zicheng Liu are with the Department of Electrical Engineering and Computer Science, Northwest- ern University, 2145 Sheridan Road

Wu, Ying

445

PIERS ONLINE, VOL. 4, NO. 5, 2008 551 A Parallel, Fourier Finite-Element Formulation with an Iterative  

E-Print Network [OSTI]

of Science and Technology in Krakow, Poland Abstract-- We describe a new method to simulate resistivity-adaptive grid-refinement strategy. We apply the new method to simulate measurements acquired with a logging-while-drilling described in [12] with a new iterative solver specially designed for the FFE formulation. In addition, we

Torres-Verdín, Carlos

446

PUBLISHED VERSION Ion cyclotron resonance frequency heating in JET during initial operations with the ITER-like wall  

E-Print Network [OSTI]

PUBLISHED VERSION Ion cyclotron resonance frequency heating in JET during initial operations.1063/1.4884354 #12;Ion cyclotron resonance frequency heating in JET during initial operations with the ITER-mode regime in Alcator C-Moda) Phys. Plasmas 20, 055904 (2013); 10.1063/1.4803914 Upgrade of the infrared

447

DQS Advisor: A visual interface and knowledge-based system to balance dose, quality, and reconstruction speed in iterative  

E-Print Network [OSTI]

the limited projection data collected at reduced X-ray radiation is challenging, and iterative algorithms have concerns with regards to the X-ray dose delivered to the patient, low-dose Computed Tomography (CT) has and K Mueller Visual Analytic and Imaging Lab, Computer Science Department, Stony Brook University, NY

Mueller, Klaus

448

ITER pioneers receive prestigious Russian energy prize of June in Saint Petersburg, three pioneers of the international fusion project  

E-Print Network [OSTI]

Vladimir Putin, president of the Russian Federation. The laureates -- the Russian academician Evgeniy speech during the prize ceremony, President Putin said: "I will emphasize that as one of the world Putin in Saint Petersburg earlier today. Evgeniy Velikhov is one of the founders of the ITER project

449

Real-time sawtooth control and neoclassical tearing mode preemption in ITER  

SciTech Connect (OSTI)

Real-time control of multiple plasma actuators is a requirement in advanced tokamaks; for example, for burn control, plasma current profile control and MHD stabilization—electron cyclotron (EC) wave absorption is ideally suited especially for the latter. On ITER, 24 EC sources can be switched between 56 inputs at the torus. In the torus, 5 launchers direct the power to various locations across the plasma profile via 11 steerable mirrors. For optimal usage of the available power, the aiming and polarization of the beams must be adapted to the plasma configuration and the needs of the scenario. Since the EC system performs many competing tasks, present day systems should demonstrate the ability of an EC plant to deal with several targets in parallel and/or to switch smoothly between goals to attain overall satisfaction. Based on pacing and locking experiments performed on TCV (Tokamak à Configuration Variable), the real-time sawtooth control of ITER with this complex set of actuators is analyzed, as an example. It is shown that sawtooth locking and pacing are possible with various levels of powers, leading to different time delays between the end of the EC power phase and the next sawtooth crash. This timing is important since it allows use of the same launchers for neoclassical tearing mode (NTM) preemption at the q?=?1.5 or 2 surface, avoiding the need to switch power between launchers. These options are presented. It is also demonstrated that increasing the total EC power does not necessarily increase the range of control because of the geometry of the launchers.

Kim, D., E-mail: doohyun.kim@epfl.ch; Goodman, T. P.; Sauter, O. [École Polytechnique Fédérale de Lausanne (EPFL), Centre de Recherches en Physique des Plasmas (CRPP), CH-1015 Lausanne (Switzerland)

2014-06-15T23:59:59.000Z

450

Benchmarking MELCOR 1.8.2 for ITER Against Recent EVITA Results  

SciTech Connect (OSTI)

A version of MELCOR 1.8.2 modified for use in ITER Preliminary Safety Report analyses was validated against recent data from the EVITA facility located in Cadarache, France. EVITA Test Series 7 was used for this study to verify MELCOR’s ability to predict the pressures, temperatures, cryoplate ice mass, and vaccum vessel (VV) condensate mass for test conditions in EVITA that include injections of steam, nitrogen, and water in to the EVITA VV after the walls had been heated to 165 ºC and the cryoplate had been cooled to -193 ºC. In general, the ability of MELCOR to predict the VV pressure and wall temperatures for the steam only and water only injection tests was very good. Predicted ice layer masses where larger than reported for the EVITA cryoplate, in particular for the steam only injection tests (~40% too high), and the predicted condensate masses were less that measured in EVITA. Both of these descrpancies can be explained by ice porosity. The modified MELCOR 1.8.2 over predicts the EVITA VV pressure for the co-injection tests (e.g., steam plus nitrogen, or water plus nitrogen injections) by almost a factor of two. Based on parametric runs that where made by increasing the predicted cryoplate condensation rate, it is believed that this pressure over prediction is a result of an under predicted cryoplate condensation rate. The particulars of this study are documented in this report as well as conclusions about the impact this study has regarding the use of this verions of MELCOR for consequence analyses for ITER safety reports.

Merrill, Brad J

2007-11-01T23:59:59.000Z

451

Evaluation of static mixer flow enhancements for cryogenic viscous compressor prototype for ITER vacuum system  

SciTech Connect (OSTI)

As part of the U.S. ITER contribution to the vacuum systems for the ITER fusion project, a cryogenic viscous compressor (CVC) is being designed and fabricated to cryopump hydrogenic gases in the torus and neutral beam exhaust streams and to regenerate the collected gases to controlled pressures such that they can be mechanically pumped with controlled flows to the tritium reprocessing facility. One critical element of the CVC design that required additional investigation was the determination of flow rates of the low pressure (up to 1000 Pa) exhaust stream that would allow for complete pumping of hydrogenic gases while permitting trace levels of helium to pass through the CVC to be pumped by conventional vacuum pumps. A sub-scale prototype test facility was utilized to determine the effectiveness of a static mixer pump tube concept, which consisted of a series of rotated twisted elements brazed into a 2-mm thick, 5-cm diameter stainless steel tube. Cold helium gas flow provided by a dewar and helium transfer line was used to cool the exterior of the static mixer pump tube. Deuterium gas was mixed with helium gas through flow controllers at different concentrations while the composition of the exhaust gas was monitored with a Penning gauge and optical spectrometer to determine the effectiveness of the static mixer. It was found that with tube wall temperatures between 6 K and 9 K, the deuterium gas was completely cryopumped and only helium passed through the tube. These results have been used to design the cooling geometry and the static mixer pump tubes in the full-scale CVC prototype.

Duckworth, Robert C.; Baylor, Larry R.; Meitner, Steven J.; Combs, Stephen K.; Ha, Tam; Morrow, Michael; Biewer, T. [Fusion and Materials for Nuclear System Division, Oak Ridge National Laboratory, Oak Ridge (United States); Rasmussen, David A.; Hechler, Michael P. [U.S. ITER Project Office, Oak Ridge National Laboratory, Oak Ridge (United States); Pearce, Robert J. H.; Dremel, Mattias [ITER Organization, 13115 St. Paul-lez-Durance (France); Boissin, J.-C. [Consultant, Grenoble (France)

2014-01-29T23:59:59.000Z

452

ICRF Specific Plasma Wall Interactions in JET with the ITER-Like Wall  

SciTech Connect (OSTI)

A variety of plasma wall interactions (PWIs) during operation of the so-called A2 ICRF antennas is observed in JET with the ITER-like wall. Amongst effects of the PWIs, the W content increase is the most significant, especially at low plasma densities. No increase of W source from the main divertor and entrance of the outer divertor during ICRF compared to NBI phases was found by means of spectroscopic and WI (400.9 nm) imaging diagnostics. In contrary, the W flux there is higher during NBI. Charge exchange neutrals of hydrogen isotopes could be excluded as considerable contributors to the W source. The high W content in ICRF heated limiter discharges suggests the possibility of other W sources than the divertor alone. Dependencies of PWIs to individual ICRF antennas during q95-scans, and intensification of those for the 90 phasing, indicate a link between the PWIs and the antenna near-fields. The PWIs include heat loads and Be sputtering pattern on antenna limiters. Indications of some PWIs at the outer divertor entrance are observed which do not result in higher W flux compared to the NBI phases, but are characterized by small antenna-specific (up to 25% with respect to ohmic phases) bipolar variations of WI emission. The first TOPICA calculations show a particularity of the A2 antennas compared to the ITER antenna, due to the presence of long antenna limiters in the RF image current loop and thus high near-fields across the most part of the JET outer wall.

Bobkov, V. [Max-Planck-Institut fur Plasmaphysik, EURATOM Association, Garching, Germany] [Max-Planck-Institut fur Plasmaphysik, EURATOM Association, Garching, Germany; Arnoux, G. [EURATOM, Culham Sci Ctr, Abingdon, Oxon England] [EURATOM, Culham Sci Ctr, Abingdon, Oxon England; Brezinsek, S. [Forschungszentrum Julich, Julich, Germany] [Forschungszentrum Julich, Julich, Germany; Coenen, J. W. [Institute of Energy and Climate Research, Germany] [Institute of Energy and Climate Research, Germany; Colas, L. [French Atomic Energy Commission (CEA)] [French Atomic Energy Commission (CEA); Clever, M. [Institute of Energy and Climate Research, Germany] [Institute of Energy and Climate Research, Germany; Czarnecka, A. [Association EURATOM-IPPLM, Warsaw, Poland] [Association EURATOM-IPPLM, Warsaw, Poland; Braun, F. [Max-Planck-Institut fur Plasma Physik, Garching, Germany] [Max-Planck-Institut fur Plasma Physik, Garching, Germany; Dux, R. [Max-Planck-Institut fur Plasma Physik, Garching, Germany] [Max-Planck-Institut fur Plasma Physik, Garching, Germany; Huber, Alexander [EURATOM / FZ-Juelich, Germany] [EURATOM / FZ-Juelich, Germany; Jacquet, P. [EURATOM / UKAEA, Abingdon, UK] [EURATOM / UKAEA, Abingdon, UK; Klepper, C Christopher [ORNL] [ORNL; Lerche, E. [ERM-KMS, Association EURATOM-Belgian State, Brussels, Belgium] [ERM-KMS, Association EURATOM-Belgian State, Brussels, Belgium; Maggi, C. [Max-Planck-Institut fur Plasma Physik, Garching, Germany] [Max-Planck-Institut fur Plasma Physik, Garching, Germany; Marcotte, F. [CEA IRFM, St. Paul-lez-Durance, France] [CEA IRFM, St. Paul-lez-Durance, France; Maslov, M. [Association EURATOM-CCFE, Abingdon, UK] [Association EURATOM-CCFE, Abingdon, UK; Matthews, G. [Association EURATOM-CCFE, Abingdon, UK] [Association EURATOM-CCFE, Abingdon, UK; Mayoral, M.-L. [EURATOM / UKAEA, UK] [EURATOM / UKAEA, UK; McCormick, K. D. [Max-Planck-Institut fur Plasma Physik, Garching, Germany] [Max-Planck-Institut fur Plasma Physik, Garching, Germany; Meigs, A. G. [EURATOM / UKAEA, UK] [EURATOM / UKAEA, UK; Milanesio, D. [Politecnico di Torino] [Politecnico di Torino; Monakhov, I. [EURATOM / UKAEA, Abingdon, UK] [EURATOM / UKAEA, Abingdon, UK; Neu, Rudolf [EURATOM / IPP Garching, Germany] [EURATOM / IPP Garching, Germany; Noterdaeme, J.-M. [Max-Planck-Institut fur Plasma Physik, Garching, Germany] [Max-Planck-Institut fur Plasma Physik, Garching, Germany; Putterich, Th. [Max-Planck-Institut fur Plasma Physik, Garching, Germany] [Max-Planck-Institut fur Plasma Physik, Garching, Germany; Rimini, F. [Association EURATOM-CCFE, Abingdon, UK] [Association EURATOM-CCFE, Abingdon, UK; Rooj, G. Van [Institute for Plasma Physics Rijnhuizen, Nieuwegein, Netherlands] [Institute for Plasma Physics Rijnhuizen, Nieuwegein, Netherlands; Sergienko, G. [Institute of Energy and Climate Research, Germany] [Institute of Energy and Climate Research, Germany; Van Eester, D. [ERM-KMS, Association EURATOM-Belgian State, Brussels, Belgium] [ERM-KMS, Association EURATOM-Belgian State, Brussels, Belgium

2013-01-01T23:59:59.000Z

453

Evaluation of Static Mixer Flow Enhancements for Cryogenic Viscous Compressor Prototype for ITER Vacuum System  

SciTech Connect (OSTI)

As part of the U.S. ITER contribution to the vacuum systems for the ITER fusion project, a cryogenic viscous compressor (CVC) is being designed and fabricated to cryopump hydrogenic gases in the torus and neutral beam exhaust streams and to regenerate the collected gases to controlled pressures such that they can be mechanically pumped with controlled flows to the tritium reprocessing facility. One critical element of the CVC design that required additional investigation was the determination of flow rates of the low pressure (50 to 1000 Pa) exhaust stream that would allow for complete pumping of hydrogenic gases while permitting trace levels of helium to pass through the CVC to be pumped by conventional vacuum pumps. A sub-scale prototype test facility was utilized to determine the effectiveness of a static mixer pump tube concept, which consisted of a series of rotated twisted elements brazed into a 2-mm thick, 5-cm diameter stainless steel tube. Cold helium gas flow provided by a dewar and helium transfer line was used to cool the exterior of the static mixer pump tube. Deuterium gas was mixed with helium gas through flow controllers at different concentrations while the composition of the exhaust gas was monitored with a Penning gauge and optical spectrometer to determine the effectiveness of the static mixer. It was found that with tube wall temperatures between 6 K and 9 K, the deuterium gas was completely cryopumped and only helium passed through the tube. These results have been used to design the cooling geometry and the static mixer pump tubes in the full-scale CVC prototype

Duckworth, Robert C [ORNL] [ORNL; Baylor, Larry R [ORNL] [ORNL; Meitner, Steven J [ORNL] [ORNL; Combs, Stephen Kirk [ORNL] [ORNL; Ha, Tam T [ORNL] [ORNL; Morrow, Michael [ORNL] [ORNL; Biewer, Theodore M [ORNL] [ORNL; Rasmussen, David A [ORNL] [ORNL; Hechler, Michael P [ORNL] [ORNL; Pearce, R.J.H. [ITER Organization, Cadarache, France] [ITER Organization, Cadarache, France; Dremel, M. [ITER Organization, Cadarache, France] [ITER Organization, Cadarache, France; Boissin, Jean Claude [Consultant] [Consultant

2014-01-01T23:59:59.000Z

454

Public involvement in radioactive waste management decisions  

SciTech Connect (OSTI)

Current repository siting efforts focus on Yucca Mountain, Nevada, where DOE`s Office of Civilian Radioactive Waste Management (OCRWM) is conducting exploratory studies to determine if the site is suitable. The state of Nevada has resisted these efforts: it has denied permits, brought suit against DOE, and publicly denounced the federal government`s decision to study Yucca Mountain. The state`s opposition reflects public opinion in Nevada, and has considerably slowed DOE`s progress in studying the site. The Yucca Mountain controversy demonstrates the importance of understanding public attitudes and their potential influence as DOE develops a program to manage radioactive waste. The strength and nature of Nevada`s opposition -- its ability to thwart if not outright derail DOE`s activities -- indicate a need to develop alternative methods for making decisions that affect the public. This report analyzes public participation as a key component of this openness, one that provides a means of garnering acceptance of, or reducing public opposition to, DOE`s radioactive waste management activities, including facility siting and transportation. The first section, Public Perceptions: Attitudes, Trust, and Theory, reviews the risk-perception literature to identify how the public perceives the risks associated with radioactivity. DOE and the Public discusses DOE`s low level of credibility among the general public as the product, in part, of the department`s past actions. This section looks at the three components of the radioactive waste management program -- disposal, storage, and transportation -- and the different ways DOE has approached the problem of public confidence in each case. Midwestern Radioactive Waste Management Histories focuses on selected Midwestern facility-siting and transportation activities involving radioactive materials.

NONE

1994-04-01T23:59:59.000Z

455

An analysis of factors contributing to train-involved crashes  

E-Print Network [OSTI]

. Crashes involving trains and vehicles are a significant safety problem in Texas each year. This research attempts to identify and analyze contributing factors to train-involved accidents in Texas. Three years of accident data (1328 total accidents) were...

Cooner, Scott Allen

1995-01-01T23:59:59.000Z

456

Evaluating the performance of two neutron spectrum unfolding codes based on iterative procedures and artificial neural networks  

SciTech Connect (OSTI)

In this work the performance of two neutron spectrum unfolding codes based on iterative procedures and artificial neural networks is evaluated. The first one code based on traditional iterative procedures and called Neutron spectrometry and dosimetry from the Universidad Autonoma de Zacatecas (NSDUAZ) use the SPUNIT iterative algorithm and was designed to unfold neutron spectrum and calculate 15 dosimetric quantities and 7 IAEA survey meters. The main feature of this code is the automated selection of the initial guess spectrum trough a compendium of neutron spectrum compiled by the IAEA. The second one code known as Neutron spectrometry and dosimetry with artificial neural networks (NDSann) is a code designed using neural nets technology. The artificial intelligence approach of neural net does not solve mathematical equations. By using the knowledge stored at synaptic weights on a neural net properly trained, the code is capable to unfold neutron spectrum and to simultaneously calculate 15 dosimetric quantities, needing as entrance data, only the rate counts measured with a Bonner spheres system. Similarities of both NSDUAZ and NSDann codes are: they follow the same easy and intuitive user's philosophy and were designed in a graphical interface under the LabVIEW programming environment. Both codes unfold the neutron spectrum expressed in 60 energy bins, calculate 15 dosimetric quantities and generate a full report in HTML format. Differences of these codes are: NSDUAZ code was designed using classical iterative approaches and needs an initial guess spectrum in order to initiate the iterative procedure. In NSDUAZ, a programming routine was designed to calculate 7 IAEA instrument survey meters using the fluence-dose conversion coefficients. NSDann code use artificial neural networks for solving the ill-conditioned equation system of neutron spectrometry problem through synaptic weights of a properly trained neural network. Contrary to iterative procedures, in neural net approach it is possible to reduce the rate counts used to unfold the neutron spectrum. To evaluate these codes a computer tool called Neutron Spectrometry and dosimetry computer tool was designed. The results obtained with this package are showed. The codes here mentioned are freely available upon request to the authors.

Ortiz-Rodriguez, J. M.; Reyes Alfaro, A.; Reyes Haro, A.; Solis Sanches, L. O.; Miranda, R. Castaneda; Cervantes Viramontes, J. M. [Universidad Autonoma de Zacatecas, Unidad Academica de Ingenieria Electrica. Av. Ramon Lopez Velarde 801. Col. Centro Zacatecas, Zac (Mexico); Vega-Carrillo, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Ingenieria Electrica. Av. Ramon Lopez Velarde 801. Col. Centro Zacatecas, Zac., Mexico. and Unidad Academica de Estudios Nucleares. C. Cip (Mexico)

2013-07-03T23:59:59.000Z

457

Hydrogen Bonds Involved in Binding the Qi-site Semiquinone in the bc1 Complex, Identified through Deuterium Exchange  

E-Print Network [OSTI]

Hydrogen Bonds Involved in Binding the Qi-site Semiquinone in the bc1 Complex, Identified through them. The strength of interactions indicates that the protons are involved in hydrogen bonds with SQ. The hyperfine cou- plings differ from values typical for in-plane hydrogen bonds previously observed in model

Crofts, Antony R.

458

Simultaneous impact of neutron irradiation and sputtering on the surface structure of self–damaged ITER–grade tungsten  

SciTech Connect (OSTI)

Simultaneous effects of neutron irradiation and long–term sputtering on the surface relief of ITER–grade tungsten were studied. The effects of neutron–induced displacement damage have been simulated by irradiation of tungsten target with W{sup 6+} ions of 20?MeV energy. Ar{sup +} ions with energy 600?eV were used as imitation of charge exchange atoms in ITER. The surface relief was studied after each sputtering act. The singularity in the WJ–IG surface relief was ascertained experimentally at the first time, which determines the law of roughness extension under sputtering. As follows from the experimental data, the neutron irradiation has not to make a decisive additional contribution in the processes developing under impact of charge exchange atoms only.

Belyaeva, A. I., E-mail: aibelyaeva@mail.ru; Savchenko, A. A. [National Technical University “Kharkov Politechnical Institute”, Kharkov, 61002 (Ukraine); Galuza, A. A.; Kolenov, I. V. [Institute of Electrophysics and Radiation Technologies, National Academy of Science of Ukraine, Kharkov, 61024 (Ukraine)

2014-07-15T23:59:59.000Z

459

ITER: The International Thermonuclear Experimental Reactor and the nuclear weapons proliferation implications of thermonuclear-fusion energy  

E-Print Network [OSTI]

This paper contains two parts: (I) A list of "points" highlighting the strategic-political and military-technical reasons and implications of the very probable siting of ITER (the International Thermonuclear Experimental Reactor) in Japan, which should be confirmed sometimes in early 2004. (II) A technical analysis of the nuclear weapons proliferation implications of inertial- and magnetic-confinement fusion systems substantiating the technical points highlighted in the first part, and showing that while full access to the physics of thermonuclear weapons is the main implication of ICF, full access to large-scale tritium technology is the main proliferation impact of MCF. The conclusion of the paper is that siting ITER in a country such as Japan, which already has a large separated-plutonium stockpile, and an ambitious laser-driven ICF program (comparable in size and quality to those of the United States or France) will considerably increase its latent (or virtual) nuclear weapons proliferation status, and fo...

Gsponer, A; Gsponer, Andre; Hurni, Jean-Pierre

2004-01-01T23:59:59.000Z

460

Iterative methods for the solution of very large complex symmetric linear systems of equations in electrodynamics  

SciTech Connect (OSTI)

In the field of computational electrodynamics the discretization of Maxwell`s equations using the Finite Integration Theory (FIT) yields very large, sparse, complex symmetric linear systems of equations. For this class of complex non-Hermitian systems a number of conjugate gradient-type algorithms is considered. The complex version of the biconjugate gradient (BiCG) method by Jacobs can be extended to a whole class of methods for complex-symmetric algorithms SCBiCG(T, n), which only require one matrix vector multiplication per iteration step. In this class the well-known conjugate orthogonal conjugate gradient (COCG) method for complex-symmetric systems corresponds to the case n = 0. The case n = 1 yields the BiCGCR method which corresponds to the conjugate residual algorithm for the real-valued case. These methods in combination with a minimal residual smoothing process are applied separately to practical 3D electro-quasistatical and eddy-current problems in electrodynamics. The practical performance of the SCBiCG methods is compared with other methods such as QMR and TFQMR.

Clemens, M.; Weiland, T. [Technische Hochschule Darmstadt (Germany)

1996-12-31T23:59:59.000Z

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461

Millimeter wave experiment of ITER equatorial EC launcher mock-up  

SciTech Connect (OSTI)

The full-scale mock-up of the equatorial launcher was fabricated in basis of the baseline design to investigate the mm-wave propagation properties of the launcher, the manufacturability, the cooling line management, how to assemble the components and so on. The mock-up consists of one of three mm-wave transmission sets and one of eight waveguide lines can deliver the mm-wave power. The mock-up was connected to the ITER compatible transmission line and the 170GHz gyrotron and the high power experiment was carried out. The measured radiation pattern of the beam at the location of 2.5m away from the EL mock-up shows the successful steering capability of 20°?40°. It was also revealed that the radiated profile at both steering and fixed focusing mirror agreed with the calculation. The result also suggests that some unwanted modes are included in the radiated beam. Transmission of 0.5MW-0.4sec and of 0.12MW-50sec were also demonstrated.

Takahashi, K.; Oda, Y.; Kajiwara, K.; Kobayashi, N.; Isozaki, M.; Sakamoto, K. [Japan Atomic Energy Agency, Naka (Japan); Omori, T.; Henderson, M. [ITER Organization, St. Paul lez Durance (France)

2014-02-12T23:59:59.000Z

462

Requirements and interfaces to cryogenic and power supply plants for the ITER magnet system  

SciTech Connect (OSTI)

This paper describes the requirements and interfaces of cryogenic and power supply plants for the ITER magnet system. The heat loads and mass flow rates of the magnet system is evaluated to keep coil temperature within 6.5 K during the plasma operation of 2200 s. The helium consumption in the current leads is estimated for a current feed of 4.5 MA from 4 K to 300 K. The location of the electrical insulation breaks is compared near winding and outside of cryostat. The terminal box is designed for interfacing the cryogenic and power supply systems. Separate vacuums for the cryostat and the cryolines facilitate maintenance of all cryogenic components without warm-up of the whole system. A superconducting busbar is used to supply current from a current connector at the coil to the vapor-cooled lead in the coil terminal box. The layout of cryogenic lines and equipment is designed to consider space limitations and routing restrictions in the tokamak hall and the electrical termination building. The main parameters of the cryogenic plant (cryoplant) are discussed.

Yoshida, K.; Kalinin, V.; Stoner, S. [ITER Joint Central Team, Naka-machi, Naka-gun, Ibaraki-ken (Japan)] [and others

1996-12-31T23:59:59.000Z

463

Design of Electron Cyclotron Heating and Current Drive System of ITER  

SciTech Connect (OSTI)

Since the end of EDA, the design of the Electron Cyclotron Heating and Current Drive (ECH and CD) system has been modified to respond to progress in physics understanding and change of interface conditions. Nominal RF power of 20 MW is shared by four upper launchers or one equatorial launcher RF beams are steered by front steering mirrors providing wide sweeping angle for the RF beam. DC high voltage power supply may be composed of IGBT pulse step modulators because of high frequency modulation and design flexibility to three different types of 170 GHz gyrotrons provided by three parties. The RF power from the 170 GHz gyrotron is transmitted to the launcher by 63.5 mm{phi} corrugated waveguide line and remotely switched by a waveguide switch between the upper launcher and the equatorial launcher. The ECH and CD system has also a start-up sub-system for assist of initial discharge composed of three 127.5 GHz gyrotrons and a dedicated DC high voltage power supply. Three of transmission lines are shared between 170 GHz gyrotron and 127.5 GHz gyrotron so as to inject RF beam for the start-up through the equatorial launcher. R and Ds of components for high power long pulse and mirror steering mechanism have been on-going in the parties to establish a reliable ITER ECH and CD system.

Kobayashi, N. [ITER, Cadarache (France); Bigelow, T.; Rasmussen, D. [ORNL, Oak Ridge (United States); Bonicelli, T.; Ramponi, G.; Saibene, G. [EFDA, Garching (Germany); Cirant, S. [ENEA-CNR, Milan (Italy); Denisov, G. [IAP, Nizhny Novgorod (Russian Federation); Heidinger, R.; Piosczyk, B. [FZK, Karlsruhe (Germany); Henderson, M.; Hogge, J.-P.; Thumm, M.; Tran, M. Q. [CRPP, Lausanne (Switzerland); Rao, S. L. [IPR, Bhat (India); Sakamoto, K.; Takahashi, K. [JAEA, Naka (Japan); Temkin, R. J. [MIT PSFC, Cambridge (United States); Verhoeven, A. G. A. [FOM IPP, Rijnhuizen (Netherlands); Zohm, H. [MPI IPP, Garching (Germany)

2007-09-28T23:59:59.000Z

464

Comparison of ICRF and NBI heated plasmas performances in the JET ITER-like wall  

SciTech Connect (OSTI)

During the initial operation of the JET ITER-like wall, particular attention was given to the characterization of the Ion Cyclotron Resonance Frequency (ICRF) heating in this new metallic environment. In this contribution we compare L-modes plasmas heated by ICRF or by Neutral Beam Injection (NBI). ICRF heating as expected led to a much higher centrally peaked power deposition on the electrons and due to the central fast ion population to stronger sawtooth activity. Surprisingly, although a higher bulk radiation was observed during the ICRF phase, the thermal plasma energy was found similar for both cases, showing that a higher radiation inside the separatrix was not incompatible with an efficient central heating scheme. The higher radiation was attributed to the presence Tungsten (W). Tomographic inversion of SXR emissions allowed a precise observation of the sawtooth effect on the radiation pattern. W concentration profiles deconvolved from SXR emission showed the flattening of the profiles due to sawtooth for both heating and the peaking of the profiles in the NBI case only hinting for extra transport effect in the ICRF case.

Mayoral, M.-L. [EFDA Close Support Unit, Garching, Germany and Euratom/CCFE Association, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); Pütterich, T.; Bobkov, V. [Max-Planck-Institut für Plasmaphysik, EURATOM-Assoziation, Garching (Germany); Jacquet, P. [Euratom/CCFE Association, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); Lerche, E.; Van-Eester, D.; Bourdelle, C.; Colas, L. [CEA, IRFM, F-13108 Saint-Paul-Lez-Durance (France); Czarnecka, A. [Association Euratom-IPPLM, Hery 23, 01-497 Warsaw (Poland); Mlynar, J. [Association Euratom-IPP.CR, Institute of Plasma Physics AS CR, 18200 Prague (Czech Republic); Neu, R. [EFDA Close Support Unit, Garching, Germany and Max-Planck-Institut für Plasmaphysik, EURATOM-Assoziation, Garching (Germany); Collaboration: JET-EFDA Contributors

2014-02-12T23:59:59.000Z

465

Optimization of the ITER electron cyclotron equatorial launcher for improved heating and current drive functional capabilities  

SciTech Connect (OSTI)

The design of the ITER Electron Cyclotron Heating and Current Drive (EC H and CD) system has evolved in the last years both in goals and functionalities by considering an expanded range of applications. A large effort has been devoted to a better integration of the equatorial and the upper launchers, both from the point of view of the performance and of the design impact on the engineering constraints. However, from the analysis of the ECCD performance in two references H-mode scenarios at burn (the inductive H-mode and the advanced non-inductive scenario), it was clear that the EC power deposition was not optimal for steady-state applications in the plasma region around mid radius. An optimization study of the equatorial launcher is presented here aiming at removing this limitation of the EC system capabilities. Changing the steering of the equatorial launcher from toroidal to poloidal ensures EC power deposition out to the normalized toroidal radius ????0.6, and nearly doubles the EC driven current around mid radius, without significant performance degradation in the core plasma region. In addition to the improved performance, the proposed design change is able to relax some engineering design constraints on both launchers.

Farina, D.; Figini, L. [Istituto di Fisica del Plasma, Consiglio Nazionale delle Ricerche, EURATOM-ENEA-CNR Association, via Cozzi 53, 20125 Milano (Italy); Henderson, M. [ITER Organization, 13108 Saint-Paul-lez-Durance (France); Saibene, G. [Fusion for Energy, c/Josep Pla 2, Torres Diagonal Litoral-B3, E-08019 Barcelona (Spain)

2014-06-15T23:59:59.000Z

466

Derivation of coarse-grained potentials via multistate iterative Boltzmann inversion  

E-Print Network [OSTI]

In this work, an extension to the standard iterative Boltzmann inversion (IBI) method to derive coarse-grained potentials is proposed. It is shown that the inclusion of target data from multiple states yields a less state-dependent potential, and is thus better suited to simulate systems over a range of thermodynamic states than the standard IBI method. The inclusion of target data from multiple states forces the algorithm to sample regions of potential phase space that match the radial distribution function at multiple state points, thus producing a derived potential that is more representative of the underlying potential interactions. It is shown that the algorithm is able to converge to the true potential for a system where the underlying potential is known. It is also shown that potentials derived via the proposed method better predict the behavior of n-alkane chains than those derived via the standard method. Additionally, through the examination of alkane monolayers, it is shown that the relative weight given to each state in the fitting procedure can impact bulk system properties, allowing the potentials to be further tuned in order to match the properties of reference atomistic and/or experimental systems.

Timothy C. Moore; Christopher R. Iacovella; Clare McCabe

2014-10-07T23:59:59.000Z

467

Perturbative Study of Energetic Particle Redistribution by Alfven Eigenmodes in ITER  

SciTech Connect (OSTI)

The modification of particle distributions by magnetohydrodynamic modes is an important topic for magnetically confined plasmas. Low amplitude modes are known to be capable of producing significant modification of injected neutral beam profiles. Flattening of a distribution due to phase mixing in an island or due to portions of phase space becoming stochastic is a process extremely rapid on the time scale of an experiment. In this paper we examine the effect of toroidal Alfven eigenmodes (TAE) and reversed shear Alfven eigenmodes (RSAE) in ITER on alpha particle and injected beam distributions using theoretically predicted mode amplitudes. It is found that for the equilibrium of a hybrid scenario even at ten times the predicted saturation level the modes have negligible effect on these distributions. A strongly reversed shear (or advanced) scenario, having a spectrum of modes that are much more global, is somewhat more susceptible to induced loss due to mode resonance, with alpha particle losses of over one percent with predicted amplitudes and somewhat larger with the assistance of toroidal field ripple. The elevated q profile contributes to stronger TAE (RSAE) drive and more unstable modes. An analysis of the existing mode-particle resonances is carried out to determine which modes are responsible for the profile modification and induced loss. We find that losses are entirely due to resonance with the counter-moving and trapped particle populations, with co-moving passing particles participating in resonances only deep within the plasma and not leading to loss.

N.N. Gorelenkov and R.B. White

2012-10-29T23:59:59.000Z

468

Wide-angle ITER-prototype tangential infrared and visible viewing system for DIII-D  

SciTech Connect (OSTI)

An imaging system with a wide-angle tangential view of the full poloidal cross-section of the tokamak in simultaneous infrared and visible light has been installed on DIII-D. The optical train includes three polished stainless steel mirrors in vacuum, which view the tokamak through an aperture in the first mirror, similar to the design concept proposed for ITER. A dichroic beam splitter outside the vacuum separates visible and infrared (IR) light. Spatial calibration is accomplished by warping a CAD-rendered image to align with landmarks in a data image. The IR camera provides scrape-off layer heat flux profile deposition features in diverted and inner-wall-limited plasmas, such as heat flux reduction in pumped radiative divertor shots. Demonstration of the system to date includes observation of fast-ion losses to the outer wall during neutral beam injection, and shows reduced peak wall heat loading with disruption mitigation by injection of a massive gas puff.

Lasnier, C. J., E-mail: lasnier@LLNL.gov; Allen, S. L.; Ellis, R. E.; Fenstermacher, M. E.; McLean, A. G.; Meyer, W. H.; Morris, K.; Seppala, L. G. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551-0808 (United States); Crabtree, K. [College of Optics, University of Arizona, Tucson, Arizona 85721 (United States); Van Zeeland, M. A. [General Atomics, P.O. Box 85608, San Diego, California 92186-5608 (United States)

2014-11-15T23:59:59.000Z

469

Iterative optimizing quantization method for reconstructing three-dimensional images from a limited number of views  

DOE Patents [OSTI]

A three-dimensional image reconstruction method comprises treating the object of interest as a group of elements with a size that is determined by the resolution of the projection data, e.g., as determined by the size of each pixel. One of the projections is used as a reference projection. A fictitious object is arbitrarily defined that is constrained by such reference projection. The method modifies the known structure of the fictitious object by comparing and optimizing its four projections to those of the unknown structure of the real object and continues to iterate until the optimization is limited by the residual sum of background noise. The method is composed of several sub-processes that acquire four projections from the real data and the fictitious object: generate an arbitrary distribution to define the fictitious object, optimize the four projections, generate a new distribution for the fictitious object, and enhance the reconstructed image. The sub-process for the acquisition of the four projections from the input real data is simply the function of acquiring the four projections from the data of the transmitted intensity. The transmitted intensity represents the density distribution, that is, the distribution of absorption coefficients through the object. 5 figs.

Lee, H.R.

1997-11-18T23:59:59.000Z

470

Iterative optimizing quantization method for reconstructing three-dimensional images from a limited number of views  

DOE Patents [OSTI]

A three-dimensional image reconstruction method comprises treating the object of interest as a group of elements with a size that is determined by the resolution of the projection data, e.g., as determined by the size of each pixel. One of the projections is used as a reference projection. A fictitious object is arbitrarily defined that is constrained by such reference projection. The method modifies the known structure of the fictitious object by comparing and optimizing its four projections to those of the unknown structure of the real object and continues to iterate until the optimization is limited by the residual sum of background noise. The method is composed of several sub-processes that acquire four projections from the real data and the fictitious object: generate an arbitrary distribution to define the fictitious object, optimize the four projections, generate a new distribution for the fictitious object, and enhance the reconstructed image. The sub-process for the acquisition of the four projections from the input real data is simply the function of acquiring the four projections from the data of the transmitted intensity. The transmitted intensity represents the density distribution, that is, the distribution of absorption coefficients through the object.

Lee, Heung-Rae (Dublin, CA)

1997-01-01T23:59:59.000Z

471

MAPCUMBA : a fast iterative multi-grid map-making algorithm for CMB experiments  

E-Print Network [OSTI]

The data analysis of current Cosmic Microwave Background (CMB) experiments like BOOMERanG or MAXIMA poses severe challenges which already stretch the limits of current (super-) computer capabilities, if brute force methods are used. In this paper we present a practical solution to the optimal map making problem which can be used directly for next generation CMB experiments like ARCHEOPS and TopHat, and can probably be extended relatively easily to the full PLANCK case. This solution is based on an iterative multi-grid Jacobi algorithm which is both fast and memory sparing. Indeed, if there are N_tod data points along the one dimensional timeline to analyse, the number of operations is O(N_tod ln N_tod) and the memory requirement is O(N_tod). Timing and accuracy issues have been analysed on simulated ARCHEOPS and TopHat data, and we discuss as well the issue of the joint evaluation of the signal and noise statistical properties.

O. Doré; R. Teyssier; F. R. Bouchet; D. Vibert; S. Prunet

2001-01-08T23:59:59.000Z

472

Performance evaluation approach for the supercritical helium cold circulators of ITER  

SciTech Connect (OSTI)

The ITER project design foresees Supercritical Helium (SHe) forced flow cooling for the main cryogenic components, namely, the superconducting (SC) magnets and cryopumps (CP). Therefore, cold circulators have been selected to provide the required SHe mass flow rate to cope with specific operating conditions and technical requirements. Considering the availability impacts of such machines, it has been decided to perform evaluation tests of the cold circulators at operating conditions prior to the series production in order to minimize the project technical risks. A proposal has been conceptualized, evaluated and simulated to perform representative tests of the full scale SHe cold circulators. The objectives of the performance tests include the validation of normal operating condition, transient and off-design operating modes as well as the efficiency measurement. A suitable process and instrumentation diagram of the test valve box (TVB) has been developed to implement the tests at the required thermodynamic conditions. The conceptual engineering design of the TVB has been developed along with the required thermal analysis for the normal operating conditions to support the performance evaluation of the SHe cold circulator.

Vaghela, H.; Sarkar, B.; Bhattacharya, R.; Kapoor, H. [ITER-India, Institute for Plasma Research, Near Indira Bridge, Bhat, Gandhinagar-382428 (India); Chalifour, M.; Chang, H.-S.; Serio, L. [ITER Organization, Route de Vinon sur Verdon - 13115 St Paul Lez Durance (France)

2014-01-29T23:59:59.000Z

473

Dynamic Planning and control Methodology : understanding and managing iterative error and change cycles in large-scale concurrent design and construction projects  

E-Print Network [OSTI]

Construction projects are uncertain and complex in nature. One of the major driving forces that may account for these characteristics is iterative cycles caused by errors and changes. Errors and changes worsen project ...

Lee, Sang Hyun, 1973-

2006-01-01T23:59:59.000Z

474

ITER: The International Thermonuclear Experimental Reactor and the Nuclear Weapons Proliferation Implications of Thermonuclear-Fusion Energy Systems  

E-Print Network [OSTI]

This paper contains two parts: (I) A list of “points ” highlighting the strategic-political and militarytechnical reasons and implications of the very probable siting of ITER (the International Thermonuclear Experimental Reactor) in Japan, which should be confirmed sometimes in early 2004. (II) A technical analysis of the nuclear weapons proliferation implications of inertial- and magnetic-confinement fusion systems substantiating the technical points highlighted in the first part, and showing that while full access to the physics of thermonuclear weapons is the main implication of ICF, full access to large-scale tritium technology is the main proliferation impact of MCF. The conclusion of the paper is that siting ITER in a country such as Japan, which already has a large separated-plutonium stockpile, and an ambitious laser-driven ICF program (comparable in size and quality to those of the United States or France) will considerably increase its latent (or virtual) nuclear weapons proliferation status, and foster further nuclear proliferation throughout the world. The safety and environmental problems related to the operation of largescale fusion facilities such as ITER (which contain massive amounts of hazardous and/or radioactive materials such as tritium, lithium, and beryllium, as well as neutron-activated structural materials) are not addressed in this paper.

André Gsponer; Jean-pierre Hurni

2004-01-01T23:59:59.000Z

475

DEA Efficiency Analysis Involving Multiple Production Processes with an Application to  

E-Print Network [OSTI]

with which input resources are allocated to the subunits. It introduces a simple model for efficientlyDEA Efficiency Analysis Involving Multiple Production Processes with an Application to Urban Mass in the Department of Information Systems and Technology within in the College of Business Administration

Illinois at Chicago, University of

476

Evaluation of inter-laminar shear strength of GFRP composed of bonded glass/polyimide tapes and cyanate-ester/epoxy blended resin for ITER TF coils  

SciTech Connect (OSTI)

The insulation system of the ITER TF coils consists of multi-layer glass/polyimide tapes impregnated a cyanate-ester/epoxy resin. The ITER TF coils are required to withstand an irradiation of 10 MGy from gamma-ray and neutrons since the ITER TF coils is exposed by fast neutron (>0.1 MeV) of 10{sup 22} n/m{sup 2} during the ITER operation. Cyanate-ester/epoxy blended resins and bonded glass/polyimide tapes are developed as insulation materials to realize the required radiation-hardness for the insulation of the ITER TF coils. To evaluate the radiation-hardness of the developed insulation materials, the inter-laminar shear strength (ILSS) of glass-fiber reinforced plastics (GFRP) fabricated using developed insulation materials is measured as one of most important mechanical properties before/after the irradiation in a fission reactor of JRR-3M. As a result, it is demonstrated that the GFRPs using the developed insulation materials have a sufficient performance to apply for the ITER TF coil insulation.

Hemmi, T.; Matsui, K.; Koizumi, N. [Japan Atomic Energy Agency, Fusion Research and Development Directorate 801-1 Mukoyama, Naka, Ibaraki, 311-0193 (Japan); Nishimura, A. [National Institute for Fusion Science, Fusion Engineering Research Center 322-6 Oroshi-cho, Toki, Gifu, 509-5292 (Japan); Nishijima, S. [Osaka University, Division of Sustainable Energy and Environmental Engineering 1-1 Yamadaoka, Suita, Osaka, 565-0871 (Japan); Shikama, T. [Tohoku University, Institute for Materials Research 2-1-1 Katahira, Aoba, Sendai, Miyagi, 980-8577 (Japan)

2014-01-27T23:59:59.000Z

477

Numerical Modeling of Seafloor Interation with Steel Catenary Riser  

E-Print Network [OSTI]

of a pipe resting on a bed of springs, and requires the iterative solution of a fourth-order ordinary differential equation. A series of simulations is used to illustrate the capabilities of the model. Due to the non-linear soil springs with stiffness...

You, Jung Hwan

2012-10-19T23:59:59.000Z

478

FOIASI - Special Inquiry Review of Allegations InvolvingPotentialMisc...  

Office of Environmental Management (EM)

Office of Environmental Management. The allegations involved potential violations of political activity restrictions, lack of impartiality in performing official duties, misuse of...

479

activity involving yb-1: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

GEOSYNTHETICS Engineering Websites Summary: failure involving a reinforced geosynthetic clay liner in a sedimentation pond at a waste containment liners to hydrate during on-site...

480

adenylyl cyclase involved: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

GEOSYNTHETICS Engineering Websites Summary: failure involving a reinforced geosynthetic clay liner in a sedimentation pond at a waste containment liners to hydrate during on-site...

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481

antigens predominant involvement: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

GEOSYNTHETICS Engineering Websites Summary: failure involving a reinforced geosynthetic clay liner in a sedimentation pond at a waste containment liners to hydrate during on-site...

482

aedes aegypti involvement: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

GEOSYNTHETICS Engineering Websites Summary: failure involving a reinforced geosynthetic clay liner in a sedimentation pond at a waste containment liners to hydrate during on-site...

483

adenosinergic system involvement: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

GEOSYNTHETICS Engineering Websites Summary: failure involving a reinforced geosynthetic clay liner in a sedimentation pond at a waste containment liners to hydrate during on-site...

484

adjuvant involved field: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

GEOSYNTHETICS Engineering Websites Summary: failure involving a reinforced geosynthetic clay liner in a sedimentation pond at a waste containment liners to hydrate during on-site...

485

alternaria alternata involves: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

GEOSYNTHETICS Engineering Websites Summary: failure involving a reinforced geosynthetic clay liner in a sedimentation pond at a waste containment liners to hydrate during on-site...

486

antinociception involves endogenous: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

GEOSYNTHETICS Engineering Websites Summary: failure involving a reinforced geosynthetic clay liner in a sedimentation pond at a waste containment liners to hydrate during on-site...

487

Critical Design Issues of Tokamak Cooling Water System of ITER's Fusion Reactor  

SciTech Connect (OSTI)

U.S. ITER is responsible for the design, engineering, and procurement of the Tokamak Cooling Water System (TCWS). The TCWS transfers heat generated in the Tokamak to cooling water during nominal pulsed operation 850 MW at up to 150 C and 4.2 MPa water pressure. This water contains radionuclides because impurities (e.g., tritium) diffuse from in-vessel components and the vacuum vessel by water baking at 200 240 C at up to 4.4MPa, and corrosion products become activated by neutron bombardment. The system is designated as safety important class (SIC) and will be fabricated to comply with the French Order concerning nuclear pressure equipment (December 2005) and the EU Pressure Equipment Directive using ASME Section VIII, Div 2 design codes. The complexity of the TCWS design and fabrication presents unique challenges. Conceptual design of this one-of-a-kind cooling system has been completed with several issues that need to be resolved to move to next stage of the design. Those issues include flow balancing between over hundreds of branch pipelines in parallel to supply cooling water to blankets, determination of optimum flow velocity while minimizing the potential for cavitation damage, design for freezing protection for cooling water flowing through cryostat (freezing) environment, requirements for high-energy piping design, and electromagnetic impact to piping and components. Although the TCWS consists of standard commercial components such as piping with valves and fittings, heat exchangers, and pumps, complex requirements present interesting design challenges. This paper presents a brief description of TCWS conceptual design and critical design issues that need to be resolved.

Kim, Seokho H [ORNL] [ORNL; Berry, Jan [ORNL] [ORNL

2011-01-01T23:59:59.000Z

488

Resolution enhancement of lung 4D-CT data using multiscale interphase iterative nonlocal means  

SciTech Connect (OSTI)

Purpose: Four-dimensional computer tomography (4D-CT) has been widely used in lung cancer radiotherapy due to its capability in providing important tumor motion information. However, the prolonged scanning duration required by 4D-CT causes considerable increase in radiation dose. To minimize the radiation-related health risk, radiation dose is often reduced at the expense of interslice spatial resolution. However, inadequate resolution in 4D-CT causes artifacts and increases uncertainty in tumor localization, which eventually results in extra damages of healthy tissues during radiotherapy. In this paper, the authors propose a novel postprocessing algorithm to enhance the resolution of lung 4D-CT data. Methods: The authors' premise is that anatomical information missing in one phase can be recovered from the complementary information embedded in other phases. The authors employ a patch-based mechanism to propagate information across phases for the reconstruction of intermediate slices in the longitudinal direction, where resolution is normally the lowest. Specifically, the structurally matching and spatially nearby patches are combined for reconstruction of each patch. For greater sensitivity to anatomical details, the authors employ a quad-tree technique to adaptively partition the image for more fine-grained refinement. The authors further devise an iterative strategy for significant enhancement of anatomical details. Results: The authors evaluated their algorithm using a publicly available lung data that consist of 10 4D-CT cases. The authors' algorithm gives very promising results with significantly enhanced image structures and much less artifacts. Quantitative analysis shows that the authors' algorithm increases peak signal-to-noise ratio by 3-4 dB and the structural similarity index by 3%-5% when compared with the standard interpolation-based algorithms. Conclusions: The authors have developed a new algorithm to improve the resolution of 4D-CT. It outperforms the conventional interpolation-based approaches by producing images with the markedly improved structural clarity and greatly reduced artifacts.

Zhang Yu [School of Biomedical Engineering, Southern Medical University, Guangzhou 510515, China and Department of Radiology and BRIC, University of North Carolina, Chapel Hill, North Carolina 27599 (United States); Yap, Pew-Thian; Wu Guorong [Department of Radiology and BRIC, University of North Carolina, Chapel Hill, North Carolina 27599 (United States); Feng Qianjin; Chen Wufan [School of Biomedical Engineering, Southern Medical University, Guangzhou 510515 (China); Lian Jun [Department of Radiation Oncology, University of North Carolina, Chapel Hill, North Carolina 27599 (United States); Shen Dinggang [Department of Radiology and BRIC, University of North Carolina, Chapel Hill, North Carolina 27599 (United States); Department of Brain and Cognitive Engineering, Korea University, Seoul 136-713 (Korea, Republic of)

2013-05-15T23:59:59.000Z

489

Two-dimensional iterative region-of-interest (ROI) reconstruction from truncated projection data  

SciTech Connect (OSTI)

A small detector or limited gantry rotation angles may cause data truncation, in which case the entire object cannot be completely reconstructed. However, a small region of interest (ROI) may be recoverable in certain truncation situations. Two analytical methods have been proposed for exact ROI reconstruction. Here we evaluate the capability of ROI reconstruction using an maximum-likelihood expectation-maximization (ML-EM) method, which directly solves the inverse problem of the system equations. ROI reconstruction using the ML-EM method is compared with that using the two analytical methods. Comparisons are based on reconstructions of four specifically designed, computer-simulated truncation cases. In the simulation, each reconstructed ROI is coupled with its counterpart in the nontruncated case to evaluate the accuracy of the reconstructed ROI. We found that, (a) in two truncation situations the ROI can be reconstructed by both the analytical methods and the two-dimensional ML-EM method, but the ML-EM method may produce a larger ROI; (b) for a truncation case that neither analytical algorithm is applicable, the ML-EM method provides a quantitative ROI reconstruction; and (c) for the well-known 'interior' truncation problem, neither the analytical methods nor the ML-EM method can perform an exact ROI reconstruction, but the ML-EM method provides informative ROI images. We also propose an analysis using the truncated projection matrix and its Moore-Penrose inverse matrix which can help to determine the recoverable ROI using iterative methods for a given truncation situation.

Zhang, B.; Zeng, G. L. [Utah Center for Advanced Imaging Research, University of Utah, Salt Lake City, Utah 84108 (United States)

2007-03-15T23:59:59.000Z

490

INVOLVED IN DE NOVO 2-containing complex involved in RNA-directed DNA methylation in Arabidopsis  

SciTech Connect (OSTI)

At least three pathways control maintenance of DNA cytosine methylation in Arabidopsis thaliana. However, the RNA-directed DNA methylation (RdDM) pathway is solely responsible for establishment of this silencing mark. We previously described INVOLVED IN DE NOVO 2 (IDN2) as being an RNA-binding RdDM component that is required for DNA methylation establishment. In this study, we describe the discovery of two partially redundant proteins that are paralogous to IDN2 and that form a stable complex with IDN2 in vivo. Null mutations in both genes, termed IDN2-LIKE 1 and IDN2-LIKE 2 (IDNL1 and IDNL2), result in a phenotype that mirrors, but does not further enhance, the idn2 mutant phenotype. Genetic analysis suggests that this complex acts in a step in the downstream portion of the RdDM pathway. We also have performed structural analysis showing that the IDN2 XS domain adopts an RNA recognition motif (RRM) fold. Finally, genome-wide DNA methylation and expression analysis confirms the placement of the IDN proteins in an RdDM pathway that affects DNA methylation and transcriptional control at many sites in the genome. Results from this study identify and describe two unique components of the RdDM machinery, adding to our understanding of DNA methylation control in the Arabidopsis genome.

Ausin, Israel; Greenberg, Maxim V.C.; Simanshu, Dhirendra K.; Hale, Christopher J.; Vashisht, Ajay A.; Simon, Stacey A.; Lee, Tzuu-fen; Feng, Suhua; Española, Sophia D.; Meyers, Blake C.; Wohlschlegel, James A.; Patel, Dinshaw J.; Jacobsen, Steven E. (UCLA); (MSKCC); (Delaware)

2012-10-23T23:59:59.000Z

491

High-performance Computing for Topology Optimization Tailored iterative solvers for topology optimization  

E-Print Network [OSTI]

with fine resolutions, for instance for 3D printing, requires solving very large finite element models

Vuik, Kees

492

Ice sheets and their dynamics Continuum thermo-mechanical model of a glacier  

E-Print Network [OSTI]

Ice sheets and their dynamics Continuum thermo-mechanical model of a glacier Shallow Ice Approximation (SIA) SIA-I Iterative Improvement Technique Benchmarks Numerical modeling of ice-sheet dynamics and Cartography, Zdiby 1.6.2010 Ondej Soucek Ph.D. defense #12;Ice sheets and their dynamics Continuum thermo

Cerveny, Vlastislav

493

LESSONS LEARNED FROM A LANDFILL SLOPE FAILURE INVOLVING  

E-Print Network [OSTI]

LESSONS LEARNED FROM A LANDFILL SLOPE FAILURE INVOLVING GEOSYTNTHETICS Virginia L. Wilson: Geosynthetics: Lessons Learned from Failures International Geosynthetics Society editors J.P. Giroud, K.L. Soderman and G.P. Raymond November 12, 1998 #12;LESSONS LEARNED FROM A LANDFILL SLOPE FAILURE INVOLVING

494

Lessons Learned from Failures Involving Geofoam in Roads and Embankments  

E-Print Network [OSTI]

Lessons Learned from Failures Involving Geofoam in Roads and Embankments Manhattan College Research July 1999) #12;Lessons Learned from Failures Involving Geofoam in Roads and Embankments Manhattan College Research Report No. CE/GE-99-1 ii This page intentionally left blank. #12;Lessons Learned from

Horvath, John S.

495

Annual Report of the EURATOM/UKAEA Fusion Programme 2008/09 8 ITER Systems  

E-Print Network [OSTI]

optimise the plasma. These systems are based on many years experience built up in the fusion laboratories the responsibility of the new `Fusion for Energy' agency (F4E) in Barcelona. Our participation is mainly via F4E Partners at the end of this reporting period involves nuclear data production, and in particular

496

ITER project to solve global energy problems 15/11/2005 18:29  

E-Print Network [OSTI]

project, which involves countries conducting extensive research on controlled thermonuclear fusion thermonuclear fusion, which is much safer than nuclear energy. Thermonuclear reactors cannot explode the way anything about thermonuclear fusion only fifty years ago. Nobel Prize winner Academician Igor Tamm and one

497

Non-Markovianity and System-Environment Correlations in a microscopic collision model  

E-Print Network [OSTI]

We show that the use of a recently proposed iterative collision model with inter-environment swaps displays a signature of strongly non-Markovian dynamics that is highly dependent on the establishment of system-environment correlations. Two models are investigated; one in which such correlations are cancelled iteratively and one in which they are kept all across the dynamics. The degree of non-Markovianity, quantified using a measure based on the trace distance, is found to be much greater for all coupling strengths, when system-environment correlations are maintained.

Ruari McCloskey; Mauro Paternostro

2014-05-26T23:59:59.000Z

498

U.S. technical report for the ITER blanket/shield: A. blanket: Topical report, July 1990--November 1990  

SciTech Connect (OSTI)

Three solid-breeder water-cooled blanket concepts have been developed for ITER based on a multilayer configuration. The primary difference among the concepts is in the fabricated form of breeder and multiplier. All the concepts have beryllium for neutron multiplication and solid-breeder temperature control. The blanket design does not use helium gaps or insulator material to control the solid breeder temperature. Lithium oxide (Li{sub 2}O) and lithium zirconate (Li{sub 2}ZrO{sub 3}) are the primary and the backup breeder materials, respectively. The lithium-6 enrichment is 95%. The use of high lithium-6 enrichment reduces the solid breeder volume required in the blanket and consequently the total tritium inventory in the solid breeder material. Also, it increases the blanket capability to accommodate power variation. The multilayer blanket configuration can accommodate up to a factor of two change in the neutron wall loading without violating the different design guidelines. The blanket material forms are sintered products and packed bed of small pebbles. The first concept has a sintered product material (blocks) for both the beryllium multiplier and the solid breeder. The second concept, the common ITER blanket, uses a packed bed breeder and beryllium blocks. The last concept is similar to the first except for the first and the last beryllium zones. Two small layers of beryllium pebbles are located behind the first wall and the back of the last beryllium zone to reduce the total inventory of the beryllium material and to improve the blanket performance. The design philosophy adopted for the blanket is to produce the necessary tritium required for the ITER operation and to operate at power reactor conditions as much as possible. Also, the reliability and the safety aspects of the blanket are enhanced by using low-pressure water coolant and the separation of the tritium purge flow from the coolant system by several barriers.

Not Available

1995-01-01T23:59:59.000Z

499

Blind Audio Source Separation using Short+Long Term AR Source Models and Iterative Itakura-Saito  

E-Print Network [OSTI]

the source separation can be performed satisfactorily, especially in clean environment, for example by using supported by its industrial partners: BMW, Cisco Systems, France T´el´ecom, Hitachi Europe, SFR, Sharp, ST

Gesbert, David

500

An Iterative Aggregation/Disaggregation Approach for the Solution of a Mixed Integer Nonlinear Oilfield  

E-Print Network [OSTI]

Oilfield Infrastructure Planning Model Susara A. van den Heever* and Ignacio E. Grossmann** Department of Chemical Engineering, Carnegie Mellon University Pittsburgh, PA, 15213 August 1999 Keywords Oilfield planning, MINLP, aggregation, decomposition Abstract A multiperiod MINLP model for offshore oilfield

Grossmann, Ignacio E.